Fix sourcepoint write in core scripts

Fix the build-assembly.py script

.gitattributes

@@ -1,4 +1 @@
-assembly/depleted/materials.xml filter=lfs diff=lfs merge=lfs -text
-2x2-periodic/depleted/materials.xml filter=lfs diff=lfs merge=lfs -text
-2x2-reflector/depleted/materials.xml filter=lfs diff=lfs merge=lfs -text
-smr/depleted/materials.xml filter=lfs diff=lfs merge=lfs -text
+smr/core-depleted/materials.xml filter=lfs diff=lfs merge=lfs -text

.gitignore

@@ -108,4 +108,4 @@ ENV/
 
 *.csv
 
-*/depleted/materials.xml
+# */depleted/materials.xml

2x2-periodic/build-depleted.py

@@ -1,141 +0,0 @@
-from collections import OrderedDict, defaultdict
-import copy
-import os
-
-import numpy as np
-import openmc
-import opendeplete
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create "dummy" inputs to export distribcell paths for burnable cells
-
-# Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-# Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-21.41728, -21.41728, +192.5]
-upper_right = [+21.41728, +21.41728, +197.5]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-# Create OpenMC "settings.xml" file
-settings_file = openmc.Settings()
-settings_file.batches = 2
-settings_file.inactive = 1
-settings_file.particles = 10
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-settings_file.export_to_xml()
-
-#  Create OpenMC "tallies.xml" file
-tallies = openmc.Tallies()
-fuel_cells = openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-# Instantiate a "dummy" distribcell tally for each cell we wish to deplete
-for cell in fuel_cells:
-    tally = openmc.Tally(name='dummy distribcell tally')
-    distribcell_filter = openmc.DistribcellFilter([cell.id])
-    tally.filters = [distribcell_filter]
-    tally.scores = ['fission']
-    tallies.append(tally)
-
-tallies.export_to_xml()
-
-# Run OpenMC to generate summary.h5 file
-openmc.run()
-
-# Open "summary.h5" file
-su = openmc.Summary('summary.h5')
-fuel_cells = su.openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-
-#### Setup OpenDeplete Materials wrapper
-
-materials = opendeplete.Materials()
-materials.temperature = OrderedDict()
-materials.sab = OrderedDict()
-materials.initial_density = OrderedDict()
-materials.burn = OrderedDict()
-materials.cross_sections = os.environ["OPENMC_CROSS_SECTIONS"]
-
-# Extract cell materials, temperatures and sab
-for cell in su.openmc_geometry.get_all_material_cells():
-    materials.burn[cell.name] = 'fuel' in cell.fill.name.lower()
-    materials.temperature[cell.name] = cell.temperature[0]
-    if len(cell.fill._sab) > 0:
-        materials.sab[cell.name] = cell.fill._sab[0]
-
-# Extract initial fuel nuclide densities in units of at/cc
-for cell in fuel_cells:
-    densities = cell.fill.get_nuclide_atom_densities()
-    materials.initial_density[cell.fill.name] = OrderedDict()
-
-    # Convert atom densities from at/b-cm to at/cc
-    for nuclide in densities:
-        materials.initial_density[cell.fill.name][nuclide.name] = \
-            densities[nuclide][1] * 1e24
-
-# Determine the maximum material ID
-all_mats = su.openmc_geometry.get_all_materials()
-max_material_id = 0
-for material in all_mats:
-    max_material_id = max(max_material_id, material.id)
-
-# FIXME: Automatically extract info needed to calculate burnable cell volumes
-# Fuel rod geometric parameters
-radius = 0.39218
-height = 5.
-
-# Use defaultdict since OpenDeplete assumes volumes specified for all cells
-volumes = defaultdict(lambda: 1)
-
-# Assign distribmats for each material
-for cell in fuel_cells:
-    new_materials = []
-    num_instances = len(cell.distribcell_paths)
-
-    for i in range(num_instances):
-        new_material = copy.deepcopy(cell.fill)
-        new_material.id = max_material_id + 1
-        max_material_id += 1
-        new_materials.append(new_material)
-
-        # Store volume of burnable fuel rods cells
-        volumes[new_material.id] =  np.pi * radius**2 * height
-
-    cell.fill = new_materials
-
-# Create dt vector for 1 month with 15 day timesteps
-dt1 = 15*24*60*60  # 15 days
-dt2 = 1.*30*24*60*60  # 1 months
-N = np.floor(dt2/dt1)
-dt = np.repeat([dt1], N)
-
-# Create settings variable
-settings = opendeplete.Settings()
-
-settings.openmc_call = ["mpirun", "openmc"]
-settings.particles = 120000
-settings.batches = 20
-settings.inactive = 10
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [17*2, 17*2, 1]
-
-settings.power = 2.337e15 * ((17.*17.*2.) / 1.5**2)  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'depleted'
-
-op = opendeplete.Operator()
-op.geometry_fill(su.openmc_geometry, volumes, materials, settings)
-
-# Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrate(op, opendeplete.ce_cm_c1)

2x2-periodic/build-fresh.py

@@ -1,143 +0,0 @@
-"""Creates a 2D 2x2 assembly colorset with periodic BCs."""
-
-import os
-import shutil
-
-import numpy as np
-import openmc
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-
-#### Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-21.41728, -21.41728, +192.5]
-upper_right = [+21.41728, +21.41728, +197.5]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-plot.width = [21.41728*2, 21.41728*2]
-plot.origin = [0., 0., 195.]
-plot.color = 'mat'
-plot.filename = '2x2-periodic'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [34, 34, 1]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= 34
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()
-
-
-#### Move all XML files to 'fresh' directory
-
-if not os.path.exists('fresh'):
-    os.makedirs('fresh')
-    
-shutil.move('materials.xml', 'fresh/materials.xml')
-shutil.move('geometry.xml', 'fresh/geometry.xml')
-shutil.move('settings.xml', 'fresh/settings.xml')
-shutil.move('tallies.xml', 'fresh/tallies.xml')
-shutil.move('plots.xml', 'fresh/plots.xml')

2x2-periodic/build-xml.py

@@ -1,287 +0,0 @@
-"""Creates a 2D 2x2 assembly colorset with periodic BCs."""
-
-import numpy as np
-
-import opencg
-import openmc
-import openmc.opencg_compatible as opencg_compatible
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenCG model.
-
-    This method extracts the fuel assembly and wraps it in an OpenCG Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenCG Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenCG Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get all OpenCG Universes
-    all_univ = beavrs.main_universe.get_all_universes()
-
-    # Iterate over all Universes
-    fuel_assembly = None
-    for univ_id, univ in all_univ.items():
-        if univ.name == assembly_name:
-            fuel_assembly = univ
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = opencg.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = opencg.XPlane(x0=root_cell.fill.min_x, boundary='reflective')
-        max_x = opencg.XPlane(x0=root_cell.fill.max_x, boundary='reflective')
-        min_y = opencg.YPlane(y0=root_cell.fill.min_y, boundary='reflective')
-        max_y = opencg.YPlane(y0=root_cell.fill.max_y, boundary='reflective')
-        max_z = opencg.ZPlane(z0=197.5, boundary='reflective')
-        min_z = opencg.ZPlane(z0=192.5, boundary='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = opencg.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = opencg.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-def build_two_by_two(assembly1_name, assembly2_name):
-    """Build a 2x2 fuel assembly geometry.
-
-    This routine puts reflective boundary conditions along all boundaries.
-
-    Parameters
-    ----------
-    assembly1_name : str
-        The BEAVRS fuel assembly to place in the bottom right and top left
-    assembly2_name : str
-        The BEAVRS fuel assembly to place in the bottom left and top right
-
-    Returns
-    -------
-    opencg.Geometry
-        A 2x2 fuel assembly OpenCG Geometry
-
-    """
-
-    fuel_assembly1 = find_assembly(assembly1_name, wrap_geometry=False)
-    fuel_assembly2 = find_assembly(assembly2_name, wrap_geometry=False)
-
-    # Find the water material
-    all_cells = beavrs.main_universe.get_all_cells()
-    for cell_uuid, cell in all_cells.items():
-        if cell.type == 'material' and cell.fill.name == 'water':
-            water = cell.fill
-
-    # Create a Cell/Universe around the first fuel assembly
-    fuel_cell1 = opencg.Cell(name='assm1 cell')
-    fuel_cell1.fill = fuel_assembly1
-    fuel_univ1 = opencg.Universe(name='assm1 universe')
-    fuel_univ1.add_cell(fuel_cell1)
-
-    # Create a Cell/Universe around the second fuel assembly
-    fuel_cell2 = opencg.Cell(name='assm2 cell')
-    fuel_cell2.fill = fuel_assembly2
-    fuel_univ2 = opencg.Universe(name='assm2 universe')
-    fuel_univ2.add_cell(fuel_cell2)
-
-    # Create a 3x3 lattice two fuel assemblies surrounded by a water reflector
-    two_by_two_lattice = opencg.Lattice(name='reflector')
-    lat_width = fuel_assembly1.max_x - fuel_assembly1.min_x
-    two_by_two_lattice.width = [lat_width, lat_width, 1000.]
-    two_by_two_lattice.offset = [0., 0., 0.]
-    two_by_two_lattice.dimension = [2, 2, 1]
-    two_by_two_lattice.universes = [[fuel_univ1, fuel_univ2],
-                                   [fuel_univ2, fuel_univ1]]
-
-    # Create a Geometry around the reflected lattice
-    root_cell = opencg.Cell(name='root cell')
-    root_cell.fill = two_by_two_lattice
-
-    # Make mixed reflective / vacuum boundaries
-    min_x = opencg.XPlane(x0=root_cell.fill.min_x, boundary='periodic')
-    max_x = opencg.XPlane(x0=root_cell.fill.max_x, boundary='periodic')
-    min_y = opencg.YPlane(y0=root_cell.fill.min_y, boundary='periodic')
-    max_y = opencg.YPlane(y0=root_cell.fill.max_y, boundary='periodic')
-    min_z = opencg.ZPlane(z0=192.5, boundary='reflective')
-    max_z = opencg.ZPlane(z0=197.5, boundary='reflective')
-
-    # Add boundaries to the root Cell
-    root_cell.add_surface(surface=min_x, halfspace=+1)
-    root_cell.add_surface(surface=max_x, halfspace=-1)
-    root_cell.add_surface(surface=min_y, halfspace=+1)
-    root_cell.add_surface(surface=max_y, halfspace=-1)
-    root_cell.add_surface(surface=min_z, halfspace=+1)
-    root_cell.add_surface(surface=max_z, halfspace=-1)
-
-    # Create a root Universe for this fuel assembly
-    root_univ = opencg.Universe(universe_id=0, name='root universe')
-    root_univ.add_cell(root_cell)
-
-    # Create an OpenCG Geometry for this fuel assembly
-    two_by_two = opencg.Geometry()
-    two_by_two.root_universe = root_univ
-
-    return two_by_two
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS(nndc_xs=True)
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel assemblies of interest from BEAVRS model
-two_by_two = build_two_by_two('Fuel 1.6% enr instr no BAs',
-                              'Fuel 3.1% enr instr 20')
-openmc_geometry = opencg_compatible.get_openmc_geometry(two_by_two)
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = two_by_two.bounds[:3]
-upper_right = two_by_two.bounds[3:]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.ptables = True
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-bounds = two_by_two.bounds
-plot.width = [two_by_two.max_x - two_by_two.min_x,
-              two_by_two.max_y - two_by_two.min_y]
-plot.origin = [bounds[0] + (bounds[3] - bounds[0]) / 2.,
-               bounds[1] + (bounds[4] - bounds[1]) / 2.,
-               bounds[2] + (bounds[5] - bounds[2]) / 2.]
-plot.color = 'mat'
-plot.filename = '2x2-periodic'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [34, 34, 1]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= 34
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()

2x2-periodic/depleted/geometry.xml

@@ -1,242 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" temperature="300.0" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" temperature="300.0" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" temperature="300.0" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" temperature="300.0" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" temperature="300.0" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" temperature="293.6" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" temperature="300.0" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" temperature="293.6" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" temperature="300.0" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" temperature="300.0" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" temperature="300.0" universe="10007" />
-    <cell id="10053" material="10017 10018 10019 10020 10021 10022 10023 10024 10025 10026 10027 10028 10029 10030 10031 10032 10033 10034 10035 10036 10037 10038 10039 10040 10041 10042 10043 10044 10045 10046 10047 10048 10049 10050 10051 10052 10053 10054 10055 10056 10057 10058 10059 10060 10061 10062 10063 10064 10065 10066 10067 10068 10069 10070 10071 10072 10073 10074 10075 10076 10077 10078 10079 10080 10081 10082 10083 10084 10085 10086 10087 10088 10089 10090 10091 10092 10093 10094 10095 10096 10097 10098 10099 10100 10101 10102 10103 10104 10105 10106 10107 10108 10109 10110 10111 10112 10113 10114 10115 10116 10117 10118 10119 10120 10121 10122 10123 10124 10125 10126 10127 10128 10129 10130 10131 10132 10133 10134 10135 10136 10137 10138 10139 10140 10141 10142 10143 10144 10145 10146 10147 10148 10149 10150 10151 10152 10153 10154 10155 10156 10157 10158 10159 10160 10161 10162 10163 10164 10165 10166 10167 10168 10169 10170 10171 10172 10173 10174 10175 10176 10177 10178 10179 10180 10181 10182 10183 10184 10185 10186 10187 10188 10189 10190 10191 10192 10193 10194 10195 10196 10197 10198 10199 10200 10201 10202 10203 10204 10205 10206 10207 10208 10209 10210 10211 10212 10213 10214 10215 10216 10217 10218 10219 10220 10221 10222 10223 10224 10225 10226 10227 10228 10229 10230 10231 10232 10233 10234 10235 10236 10237 10238 10239 10240 10241 10242 10243 10244 10245 10246 10247 10248 10249 10250 10251 10252 10253 10254 10255 10256 10257 10258 10259 10260 10261 10262 10263 10264 10265 10266 10267 10268 10269 10270 10271 10272 10273 10274 10275 10276 10277 10278 10279 10280 10281 10282 10283 10284 10285 10286 10287 10288 10289 10290 10291 10292 10293 10294 10295 10296 10297 10298 10299 10300 10301 10302 10303 10304 10305 10306 10307 10308 10309 10310 10311 10312 10313 10314 10315 10316 10317 10318 10319 10320 10321 10322 10323 10324 10325 10326 10327 10328 10329 10330 10331 10332 10333 10334 10335 10336 10337 10338 10339 10340 10341 10342 10343 10344 10345 10346 10347 10348 10349 10350 10351 10352 10353 10354 10355 10356 10357 10358 10359 10360 10361 10362 10363 10364 10365 10366 10367 10368 10369 10370 10371 10372 10373 10374 10375 10376 10377 10378 10379 10380 10381 10382 10383 10384 10385 10386 10387 10388 10389 10390 10391 10392 10393 10394 10395 10396 10397 10398 10399 10400 10401 10402 10403 10404 10405 10406 10407 10408 10409 10410 10411 10412 10413 10414 10415 10416 10417 10418 10419 10420 10421 10422 10423 10424 10425 10426 10427 10428 10429 10430 10431 10432 10433 10434 10435 10436 10437 10438 10439 10440 10441 10442 10443 10444 10445 10446 10447 10448 10449 10450 10451 10452 10453 10454 10455 10456 10457 10458 10459 10460 10461 10462 10463 10464 10465 10466 10467 10468 10469 10470 10471 10472 10473 10474 10475 10476 10477 10478 10479 10480 10481 10482 10483 10484 10485 10486 10487 10488 10489 10490 10491 10492 10493 10494 10495 10496 10497 10498 10499 10500 10501 10502 10503 10504 10505 10506 10507 10508 10509 10510 10511 10512 10513 10514 10515 10516 10517 10518 10519 10520 10521 10522 10523 10524 10525 10526 10527 10528 10529 10530 10531 10532 10533 10534 10535 10536 10537 10538 10539 10540 10541 10542 10543 10544" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" temperature="300.0" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" temperature="300.0" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" temperature="300.0" universe="10008" />
-    <cell id="10061" material="10545 10546 10547 10548 10549 10550 10551 10552 10553 10554 10555 10556 10557 10558 10559 10560 10561 10562 10563 10564 10565 10566 10567 10568 10569 10570 10571 10572 10573 10574 10575 10576 10577 10578 10579 10580 10581 10582 10583 10584 10585 10586 10587 10588 10589 10590 10591 10592 10593 10594 10595 10596 10597 10598 10599 10600 10601 10602 10603 10604 10605 10606 10607 10608 10609 10610 10611 10612 10613 10614 10615 10616 10617 10618 10619 10620 10621 10622 10623 10624 10625 10626 10627 10628 10629 10630 10631 10632 10633 10634 10635 10636 10637 10638 10639 10640 10641 10642 10643 10644 10645 10646 10647 10648 10649 10650 10651 10652 10653 10654 10655 10656 10657 10658 10659 10660 10661 10662 10663 10664 10665 10666 10667 10668 10669 10670 10671 10672 10673 10674 10675 10676 10677 10678 10679 10680 10681 10682 10683 10684 10685 10686 10687 10688 10689 10690 10691 10692 10693 10694 10695 10696 10697 10698 10699 10700 10701 10702 10703 10704 10705 10706 10707 10708 10709 10710 10711 10712 10713 10714 10715 10716 10717 10718 10719 10720 10721 10722 10723 10724 10725 10726 10727 10728 10729 10730 10731 10732 10733 10734 10735 10736 10737 10738 10739 10740 10741 10742 10743 10744 10745 10746 10747 10748 10749 10750 10751 10752 10753 10754 10755 10756 10757 10758 10759 10760 10761 10762 10763 10764 10765 10766 10767 10768 10769 10770 10771 10772 10773 10774 10775 10776 10777 10778 10779 10780 10781 10782 10783 10784 10785 10786 10787 10788 10789 10790 10791 10792 10793 10794 10795 10796 10797 10798 10799 10800 10801 10802 10803 10804 10805 10806 10807 10808 10809 10810 10811 10812 10813 10814 10815 10816 10817 10818 10819 10820 10821 10822 10823 10824 10825 10826 10827 10828 10829 10830 10831 10832 10833 10834 10835 10836 10837 10838 10839 10840 10841 10842 10843 10844 10845 10846 10847 10848 10849 10850 10851 10852 10853 10854 10855 10856 10857 10858 10859 10860 10861 10862 10863 10864 10865 10866 10867 10868 10869 10870 10871 10872 10873 10874 10875 10876 10877 10878 10879 10880 10881 10882 10883 10884 10885 10886 10887 10888 10889 10890 10891 10892 10893 10894 10895 10896 10897 10898 10899 10900 10901 10902 10903 10904 10905 10906 10907 10908 10909 10910 10911 10912 10913 10914 10915 10916 10917 10918 10919 10920 10921 10922 10923 10924 10925 10926 10927 10928 10929 10930 10931 10932 10933 10934 10935 10936 10937 10938 10939 10940 10941 10942 10943 10944 10945 10946 10947 10948 10949 10950 10951 10952 10953 10954 10955 10956 10957 10958 10959 10960 10961 10962 10963 10964 10965 10966 10967 10968 10969 10970 10971 10972 10973 10974 10975 10976 10977 10978 10979 10980 10981 10982 10983 10984 10985 10986 10987 10988 10989 10990 10991 10992 10993 10994 10995 10996 10997 10998 10999 11000 11001 11002 11003 11004 11005 11006 11007 11008 11009 11010 11011 11012 11013 11014 11015 11016 11017 11018 11019 11020 11021 11022 11023 11024 11025 11026 11027 11028 11029 11030 11031 11032 11033 11034 11035 11036 11037 11038 11039 11040 11041 11042 11043 11044 11045 11046 11047 11048 11049 11050 11051 11052 11053 11054 11055 11056 11057 11058 11059 11060 11061 11062 11063 11064 11065 11066 11067 11068 11069 11070 11071 11072" name="Fuel rod active region - 3.1% enr radial 0: Fuel 3.1%" region="-10034" temperature="300.0" universe="10010" />
-    <cell id="10062" material="10004" name="Fuel rod active region - 3.1% enr radial 1: Helium" region="10034 -10035" temperature="300.0" universe="10010" />
-    <cell id="10063" material="10006" name="Fuel rod active region - 3.1% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10010" />
-    <cell id="10064" material="10014" name="Fuel rod active region - 3.1% enr radial outer: Borated Water" region="10036" temperature="300.0" universe="10010" />
-    <cell id="10073" material="10005" name="Fuel rod plenum radial 0: Inconel 718" region="-10037" temperature="300.0" universe="10013" />
-    <cell id="10074" material="10004" name="Fuel rod plenum radial 1: Helium" region="10037 -10035" temperature="300.0" universe="10013" />
-    <cell id="10075" material="10006" name="Fuel rod plenum radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10013" />
-    <cell id="10076" material="10014" name="Fuel rod plenum radial outer: Borated Water" region="10036" temperature="300.0" universe="10013" />
-    <cell id="10077" material="10014" name="Fuel rod - 1.6% enr axial 0: Borated Water" region="-10000" temperature="300.0" universe="10014" />
-    <cell id="10078" material="10016" name="Fuel rod - 1.6% enr axial 1: SS SPN" region="-10038 10000" temperature="300.0" universe="10014" />
-    <cell fill="10007" id="10079" name="Fuel rod - 1.6% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10014" />
-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" temperature="300.0" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" temperature="300.0" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" temperature="300.0" universe="10014" />
-    <cell fill="10014" id="10086" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 1.6% enr" region="-10036" universe="10015" />
-    <cell fill="10005" id="10087" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10015" />
-    <cell id="10099" material="10014" name="Fuel rod - 3.1% enr axial 0: Borated Water" region="-10000" temperature="300.0" universe="10018" />
-    <cell id="10100" material="10016" name="Fuel rod - 3.1% enr axial 1: SS SPN" region="-10038 10000" temperature="300.0" universe="10018" />
-    <cell fill="10007" id="10101" name="Fuel rod - 3.1% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10018" />
-    <cell fill="10010" id="10102" name="Fuel rod - 3.1% enr axial 3: Fuel rod active region - 3.1% enr" region="-10040 10039" universe="10018" />
-    <cell fill="10013" id="10103" name="Fuel rod - 3.1% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10018" />
-    <cell fill="10007" id="10104" name="Fuel rod - 3.1% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10018" />
-    <cell id="10105" material="10014" name="Fuel rod - 3.1% enr axial 6: Borated Water" region="-10004 10042" temperature="300.0" universe="10018" />
-    <cell id="10106" material="10016" name="Fuel rod - 3.1% enr axial 7: SS SPN" region="-10005 10004" temperature="300.0" universe="10018" />
-    <cell id="10107" material="10014" name="Fuel rod - 3.1% enr axial top: Borated Water" region="10005" temperature="300.0" universe="10018" />
-    <cell fill="10018" id="10108" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 3.1% enr" region="-10036" universe="10019" />
-    <cell fill="10005" id="10109" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10019" />
-    <cell id="10132" material="10014" name="Empty GT below the dashpot radial 0: Borated Water" region="-10045" temperature="300.0" universe="10024" />
-    <cell id="10133" material="10006" name="Empty GT below the dashpot radial 1: Zircaloy 4" region="10045 -10046" temperature="300.0" universe="10024" />
-    <cell id="10134" material="10014" name="Empty GT below the dashpot radial outer: Borated Water" region="10046" temperature="300.0" universe="10024" />
-    <cell id="10135" material="10014" name="Empty GT above the dashpot radial 0: Borated Water" region="-10043" temperature="300.0" universe="10025" />
-    <cell id="10136" material="10006" name="Empty GT above the dashpot radial 1: Zircaloy 4" region="10043 -10044" temperature="300.0" universe="10025" />
-    <cell id="10137" material="10014" name="Empty GT above the dashpot radial outer: Borated Water" region="10044" temperature="300.0" universe="10025" />
-    <cell id="10138" material="10014" name="Empty Guide Tube axial 0: Borated Water" region="-10000" temperature="300.0" universe="10026" />
-    <cell id="10139" material="10015" name="Empty Guide Tube axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10026" />
-    <cell fill="10024" id="10140" name="Empty Guide Tube axial 2: Empty GT below the dashpot" region="-10048 10047" universe="10026" />
-    <cell fill="10025" id="10141" name="Empty Guide Tube axial 3: Empty GT above the dashpot" region="-10049 10048" universe="10026" />
-    <cell id="10142" material="10015" name="Empty Guide Tube axial 4: Water SPN" region="-10005 10049" temperature="293.6" universe="10026" />
-    <cell id="10143" material="10014" name="Empty Guide Tube axial top: Borated Water" region="10005" temperature="300.0" universe="10026" />
-    <cell fill="10026" id="10144" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial 0: Empty Guide Tube" region="-10044" universe="10027" />
-    <cell fill="10005" id="10145" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10027" />
-    <cell id="10146" material="10014" name="Empty Guide Tube in Center Position axial 0: Borated Water" region="-10000" temperature="300.0" universe="10028" />
-    <cell id="10147" material="10015" name="Empty Guide Tube in Center Position axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10028" />
-    <cell fill="10025" id="10148" name="Empty Guide Tube in Center Position axial 2: Empty GT above the dashpot" region="-10049 10047" universe="10028" />
-    <cell id="10149" material="10015" name="Empty Guide Tube in Center Position axial 3: Water SPN" region="-10005 10049" temperature="293.6" universe="10028" />
-    <cell id="10150" material="10014" name="Empty Guide Tube in Center Position axial top: Borated Water" region="10005" temperature="300.0" universe="10028" />
-    <cell fill="10028" id="10151" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial 0: Empty Guide Tube in Ce" region="-10044" universe="10029" />
-    <cell fill="10005" id="10152" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial outer: Grids axial univer" region="10044" universe="10029" />
-    <cell id="10153" material="10000" name="Instrument tube thimble radial 0: Air" region="-10050" temperature="300.0" universe="10030" />
-    <cell id="10154" material="10006" name="Instrument tube thimble radial 1: Zircaloy 4" region="10050 -10051" temperature="300.0" universe="10030" />
-    <cell id="10155" material="10014" name="Instrument tube thimble radial outer: Borated Water" region="10051" temperature="300.0" universe="10030" />
-    <cell id="10156" material="10000" name="Instrument tube thimble support plane radial 0: Air" region="-10050" temperature="300.0" universe="10031" />
-    <cell id="10157" material="10006" name="Instrument tube thimble support plane radial 1: Zircaloy 4" region="10050 -10051" temperature="300.0" universe="10031" />
-    <cell id="10158" material="10015" name="Instrument tube thimble support plane radial outer: Water SPN" region="10051" temperature="293.6" universe="10031" />
-    <cell fill="10030" id="10159" name="Instrument tube axial stack axial 0: Instrument tube thimble" region="-10000" universe="10032" />
-    <cell fill="10031" id="10160" name="Instrument tube axial stack axial 1: Instrument tube thimble support plane" region="-10038 10000" universe="10032" />
-    <cell fill="10030" id="10161" name="Instrument tube axial stack axial 2: Instrument tube thimble" region="-10004 10038" universe="10032" />
-    <cell id="10162" material="10015" name="Instrument tube axial stack axial 3: Water SPN" region="-10005 10004" temperature="293.6" universe="10032" />
-    <cell id="10163" material="10014" name="Instrument tube axial stack axial top: Borated Water" region="10005" temperature="300.0" universe="10032" />
-    <cell fill="10032" id="10164" name="(Instrument tube axial stack) wrapped by ((Empty Guide Tube in Center Position) wrapped by (Grids axial" region="-10051" universe="10033" />
-    <cell fill="10029" id="10165" name="(Instrument tube axial stack) wrapped by ((Empty Guide Tube in Center Position) wrapped by (Grids axial" region="10051" universe="10033" />
-    <cell id="10166" material="10001" name="BPRA rod lower/upper fitting radial 0: SS304" region="-10057" temperature="300.0" universe="10034" />
-    <cell id="10167" material="10014" name="BPRA rod lower/upper fitting radial outer: Borated Water" region="10057" temperature="300.0" universe="10034" />
-    <cell id="10168" material="10000" name="BPRA rod active poison radial 0: Air" region="-10052" temperature="300.0" universe="10035" />
-    <cell id="10169" material="10001" name="BPRA rod active poison radial 1: SS304" region="10052 -10053" temperature="300.0" universe="10035" />
-    <cell id="10170" material="10000" name="BPRA rod active poison radial 2: Air" region="10053 -10054" temperature="300.0" universe="10035" />
-    <cell id="10171" material="10013" name="BPRA rod active poison radial 3: Borosilicate Glass" region="10054 -10055" temperature="300.0" universe="10035" />
-    <cell id="10172" material="10000" name="BPRA rod active poison radial 4: Air" region="10055 -10056" temperature="300.0" universe="10035" />
-    <cell id="10173" material="10001" name="BPRA rod active poison radial 5: SS304" region="10056 -10057" temperature="300.0" universe="10035" />
-    <cell id="10174" material="10014" name="BPRA rod active poison radial outer: Borated Water" region="10057" temperature="300.0" universe="10035" />
-    <cell id="10175" material="10000" name="BPRA rod plenum radial 0: Air" region="-10052" temperature="300.0" universe="10036" />
-    <cell id="10176" material="10001" name="BPRA rod plenum radial 1: SS304" region="10052 -10053" temperature="300.0" universe="10036" />
-    <cell id="10177" material="10000" name="BPRA rod plenum radial 2: Air" region="10053 -10056" temperature="300.0" universe="10036" />
-    <cell id="10178" material="10001" name="BPRA rod plenum radial 3: SS304" region="10056 -10057" temperature="300.0" universe="10036" />
-    <cell id="10179" material="10014" name="BPRA rod plenum radial outer: Borated Water" region="10057" temperature="300.0" universe="10036" />
-    <cell id="10180" material="10014" name="BPRA rod axial 0: Borated Water" region="-10000" temperature="300.0" universe="10037" />
-    <cell id="10181" material="10015" name="BPRA rod axial 1: Water SPN" region="-10003 10000" temperature="293.6" universe="10037" />
-    <cell id="10182" material="10014" name="BPRA rod axial 2: Borated Water" region="-10058 10003" temperature="300.0" universe="10037" />
-    <cell fill="10034" id="10183" name="BPRA rod axial 3: BPRA rod lower/upper fitting" region="-10059 10058" universe="10037" />
-    <cell fill="10035" id="10184" name="BPRA rod axial 4: BPRA rod active poison" region="-10060 10059" universe="10037" />
-    <cell fill="10036" id="10185" name="BPRA rod axial 5: BPRA rod plenum" region="-10061 10060" universe="10037" />
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-    <cell id="10187" material="10014" name="BPRA rod axial top: Borated Water" region="10062" temperature="300.0" universe="10037" />
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2x2-periodic/depleted/settings.xml

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2x2-periodic/fresh/geometry.xml

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2x2-periodic/fresh/materials.xml

@@ -1,267 +0,0 @@
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-        <nuclide name="Sn115" wo="4.771905922545867e-05" />
-        <nuclide name="Sn116" wo="0.002058423153629443" />
-        <nuclide name="Sn117" wo="0.0010966473429083066" />
-        <nuclide name="Sn118" wo="0.0034879812938438245" />
-        <nuclide name="Sn119" wo="0.001247577110245757" />
-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10007" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
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-        <nuclide name="S32" wo="0.00023692152702311576" />
-        <nuclide name="S33" wo="1.924704844422474e-06" />
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-        <nuclide name="Si28" wo="0.0036749406913165338" />
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-        <nuclide name="Si30" wo="0.0001317892969697033" />
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-        <nuclide name="Ni60" wo="0.002008197216956016" />
-        <nuclide name="Ni61" wo="8.875193135010345e-05" />
-        <nuclide name="Ni62" wo="0.00028761167190610265" />
-        <nuclide name="Ni64" wo="7.561128087810308e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006341263666702117" />
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-        <nuclide name="Mo94" wo="0.0005619573981472699" />
-        <nuclide name="Mo95" wo="0.0009812790231824658" />
-        <nuclide name="Mo96" wo="0.0010415835207694215" />
-        <nuclide name="Mo97" wo="0.0006048497176301975" />
-        <nuclide name="Mo98" wo="0.00154921076793649" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.506648724403529e-06" />
-        <nuclide name="B11" wo="2.449335127559647e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10008" name="Fuel 1.6%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.9992419999999993" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10009" name="Fuel 2.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.9992420000000004" name="O16" />
-        <nuclide ao="0.0007580000000000002" name="O17" />
-        <nuclide ao="0.00019522327124383906" name="U234" />
-        <nuclide ao="0.024298776982208985" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10010" name="Fuel 3.1%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.9992420000000022" name="O16" />
-        <nuclide ao="0.0007580000000000009" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-    <material id="10011" name="Fuel 3.2%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.34115" />
-        <nuclide ao="1.9992419999999995" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00025991006602092703" name="U234" />
-        <nuclide ao="0.03235012244921097" name="U235" />
-        <nuclide ao="0.9673899674847681" name="U238" />
-    </material>
-    <material id="10012" name="Fuel 3.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.35917" />
-        <nuclide ao="1.999241999999999" name="O16" />
-        <nuclide ao="0.0007579999999999997" name="O17" />
-        <nuclide ao="0.0002770142199967032" name="U234" />
-        <nuclide ao="0.03447901835531245" name="U235" />
-        <nuclide ao="0.9652439674246908" name="U238" />
-    </material>
-    <material id="10013" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.013479369482225239" name="B10" />
-        <nuclide ao="0.054735873774104264" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
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-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
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-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

2x2-periodic/fresh/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="2x2-periodic" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>42.83456 42.83456</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

2x2-periodic/fresh/settings.xml

@@ -1,18 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>10</batches>
-        <inactive>5</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-21.41728 -21.41728 192.5 21.41728 21.41728 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

2x2-periodic/fresh/tallies.xml

@@ -1,299 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <!--assembly mesh-->
-    <mesh id="10000" type="regular">
-        <dimension>34 34 1</dimension>
-        <lower_left>-21.41728 -21.41728 192.5</lower_left>
-        <width>1.25984 1.25984 5.0</width>
-    </mesh>
-    <tally id="10000" name="fission rates">
-        <filter bins="10000" type="mesh" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="u-238 capture">
-        <filter bins="10000" type="mesh" />
-        <nuclides>U238</nuclides>
-        <scores>absorption fission</scores>
-    </tally>
-    <tally id="10006">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10007">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10008">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
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-    <tally id="10009">
-        <filter bins="10053" type="distribcell" />
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-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10010">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10011">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
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-        <estimator>analog</estimator>
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-    <tally id="10016">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
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-        <estimator>tracklength</estimator>
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-    <tally id="10017">
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-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
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-        <estimator>tracklength</estimator>
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-    <tally id="10018">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
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-    <tally id="10019">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
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-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10020">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10021">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10161">
-        <filter bins="10000 10001 10004 10005 10006 10008 10010 10013 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10050">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10165">
-        <filter bins="10000 10001 10004 10005 10006 10008 10010 10013 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10058">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10061">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10062">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10090">
-        <filter bins="10001 10004 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission total</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10094">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10098">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10101">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10102">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10081">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10083">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10085">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10086">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10158">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10166">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10169">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10170">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10121">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10123">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10125">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10126">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10162">
-        <filter bins="10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10150">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10153">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10154">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

2x2-periodic/geometry.py

@@ -1,153 +0,0 @@
-import openmc
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenMC model.
-
-    This method extracts the fuel assembly and wraps it in an OpenMC Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenMC Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenMC Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get OpenMC Lattices for the fuel assembly
-    fuel_assembly = \
-        beavrs.openmc_geometry.get_lattices_by_name(assembly_name)[0]
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = openmc.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = openmc.XPlane(x0=-10.70864, boundary_type='reflective')
-        max_x = openmc.XPlane(x0=+10.70864, boundary_type='reflective')
-        min_y = openmc.YPlane(y0=-10.70864, boundary_type='reflective')
-        max_y = openmc.YPlane(y0=+10.70864, boundary_type='reflective')
-        max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
-        min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = openmc.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = openmc.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-def build_two_by_two(assembly1_name, assembly2_name):
-    """Build a 2x2 fuel assembly geometry.
-
-    This routine puts reflective boundary conditions along all boundaries.
-
-    Parameters
-    ----------
-    assembly1_name : str
-        The BEAVRS fuel assembly to place in the bottom right and top left
-    assembly2_name : str
-        The BEAVRS fuel assembly to place in the bottom left and top right
-
-    Returns
-    -------
-    openmc.Geometry
-        A 2x2 fuel assembly OpenMC Geometry
-
-    """
-
-    fuel_assembly1 = find_assembly(assembly1_name, wrap_geometry=False)
-    fuel_assembly2 = find_assembly(assembly2_name, wrap_geometry=False)
-
-    # Find the water material
-    all_cells = beavrs.main_universe.get_all_cells()
-    for cell_uuid, cell in all_cells.items():
-        if cell.fill_type == 'material' and cell.fill.name == 'Borated Water':
-            water = cell.fill
-
-    # Create a Cell/Universe around the first fuel assembly
-    fuel_cell1 = openmc.Cell(name='assm1 cell')
-    fuel_cell1.fill = fuel_assembly1
-    fuel_univ1 = openmc.Universe(name='assm1 universe')
-    fuel_univ1.add_cell(fuel_cell1)
-
-    # Create a Cell/Universe around the second fuel assembly
-    fuel_cell2 = openmc.Cell(name='assm2 cell')
-    fuel_cell2.fill = fuel_assembly2
-    fuel_univ2 = openmc.Universe(name='assm2 universe')
-    fuel_univ2.add_cell(fuel_cell2)
-
-    # Create a 3x3 lattice two fuel assemblies surrounded by a water reflector
-    two_by_two_lattice = openmc.RectLattice(name='reflector')
-    two_by_two_lattice.lower_left = [-21.41728, -21.41728, -500.]
-    two_by_two_lattice.pitch = [21.41728, 21.41728, 1000.]
-    two_by_two_lattice.universes = [[[fuel_univ1, fuel_univ2],
-                                    [fuel_univ2, fuel_univ1]]]
-
-    # Create a Geometry around the reflected lattice
-    root_cell = openmc.Cell(name='root cell')
-    root_cell.fill = two_by_two_lattice
-
-    # Make mixed reflective / vacuum boundaries
-    min_x = openmc.XPlane(x0=-21.41728, boundary_type='periodic')
-    max_x = openmc.XPlane(x0=+21.41728, boundary_type='periodic')
-    min_y = openmc.YPlane(y0=-21.41728, boundary_type='periodic')
-    max_y = openmc.YPlane(y0=+21.41728, boundary_type='periodic')
-    min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
-    max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
-
-    # Add boundaries to the root Cell
-    root_cell.add_surface(surface=min_x, halfspace=+1)
-    root_cell.add_surface(surface=max_x, halfspace=-1)
-    root_cell.add_surface(surface=min_y, halfspace=+1)
-    root_cell.add_surface(surface=max_y, halfspace=-1)
-    root_cell.add_surface(surface=min_z, halfspace=+1)
-    root_cell.add_surface(surface=max_z, halfspace=-1)
-
-    # Create a root Universe for this fuel assembly
-    root_univ = openmc.Universe(universe_id=0, name='root universe')
-    root_univ.add_cell(root_cell)
-
-    # Create an OpenMC Geometry for this fuel assembly
-    two_by_two = openmc.Geometry()
-    two_by_two.root_universe = root_univ
-
-    return two_by_two
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS()
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel assemblies of interest from BEAVRS model
-openmc_geometry = build_two_by_two('Fuel 1.6% enr instr no BAs',
-                                   'Fuel 3.1% enr instr 20')

2x2-periodic/geometry.xml

@@ -1,242 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" universe="10007" />
-    <cell id="10053" material="10008" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" universe="10008" />
-    <cell id="10061" material="10010" name="Fuel rod active region - 3.1% enr radial 0: Fuel 3.1%" region="-10034" universe="10010" />
-    <cell id="10062" material="10004" name="Fuel rod active region - 3.1% enr radial 1: Helium" region="10034 -10035" universe="10010" />
-    <cell id="10063" material="10006" name="Fuel rod active region - 3.1% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10010" />
-    <cell id="10064" material="10014" name="Fuel rod active region - 3.1% enr radial outer: Borated Water" region="10036" universe="10010" />
-    <cell id="10073" material="10005" name="Fuel rod plenum radial 0: Inconel 718" region="-10037" universe="10013" />
-    <cell id="10074" material="10004" name="Fuel rod plenum radial 1: Helium" region="10037 -10035" universe="10013" />
-    <cell id="10075" material="10006" name="Fuel rod plenum radial 2: Zircaloy 4" region="10035 -10036" universe="10013" />
-    <cell id="10076" material="10014" name="Fuel rod plenum radial outer: Borated Water" region="10036" universe="10013" />
-    <cell id="10077" material="10014" name="Fuel rod - 1.6% enr axial 0: Borated Water" region="-10000" universe="10014" />
-    <cell id="10078" material="10016" name="Fuel rod - 1.6% enr axial 1: SS SPN" region="-10038 10000" universe="10014" />
-    <cell fill="10007" id="10079" name="Fuel rod - 1.6% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10014" />
-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" universe="10014" />
-    <cell fill="10014" id="10086" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 1.6% enr" region="-10036" universe="10015" />
-    <cell fill="10005" id="10087" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10015" />
-    <cell id="10099" material="10014" name="Fuel rod - 3.1% enr axial 0: Borated Water" region="-10000" universe="10018" />
-    <cell id="10100" material="10016" name="Fuel rod - 3.1% enr axial 1: SS SPN" region="-10038 10000" universe="10018" />
-    <cell fill="10007" id="10101" name="Fuel rod - 3.1% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10018" />
-    <cell fill="10010" id="10102" name="Fuel rod - 3.1% enr axial 3: Fuel rod active region - 3.1% enr" region="-10040 10039" universe="10018" />
-    <cell fill="10013" id="10103" name="Fuel rod - 3.1% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10018" />
-    <cell fill="10007" id="10104" name="Fuel rod - 3.1% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10018" />
-    <cell id="10105" material="10014" name="Fuel rod - 3.1% enr axial 6: Borated Water" region="-10004 10042" universe="10018" />
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-    <surface boundary="reflective" coeffs="197.5" id="10154" type="z-plane" />
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2x2-periodic/materials.xml

@@ -1,267 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<materials>
-    <material id="10000" name="Air">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.00616" />
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-        <nuclide ao="0.0028604367000000003" name="N15" />
-        <nuclide ao="3.1124879999999996e-05" name="Ar36" />
-        <nuclide ao="5.86857e-06" name="Ar38" />
-        <nuclide ao="0.00929300655" name="Ar40" />
-        <nuclide ao="0.00027" name="C0" />
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-    <material id="10001" name="SS304">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.03" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
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-        <nuclide name="Fe57" wo="0.014776921339264018" />
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-        <nuclide name="Ni58" wo="0.06719770531879568" />
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-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
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-    <material id="10002" name="Ag-In-Cd">
-        <temperature>300</temperature>
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-        <nuclide name="Cd116" wo="0.00387264036945234" />
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-        <nuclide name="C0" wo="0.2174" />
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-    <material id="10004" name="Helium">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.0015981" />
-        <nuclide name="He3" wo="1.5070346049256974e-06" />
-        <nuclide name="He4" wo="0.999998492965395" />
-    </material>
-    <material id="10005" name="Inconel 718">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.2" />
-        <nuclide name="Si28" wo="0.003215573104901967" />
-        <nuclide name="Si29" wo="0.00016911126024954278" />
-        <nuclide name="Si30" wo="0.00011531563484849038" />
-        <nuclide name="Cr50" wo="0.007913309553017726" />
-        <nuclide name="Cr52" wo="0.15869399115925625" />
-        <nuclide name="Cr53" wo="0.018341120727338085" />
-        <nuclide name="Cr54" wo="0.004651578560387908" />
-        <nuclide name="Mn55" wo="0.0087" />
-        <nuclide name="Fe54" wo="0.016163233201258693" />
-        <nuclide name="Fe56" wo="0.26311407687664323" />
-        <nuclide name="Fe57" wo="0.006185135350045743" />
-        <nuclide name="Fe58" wo="0.0008375545720523535" />
-        <nuclide name="Ni58" wo="0.34398505352691505" />
-        <nuclide name="Ni60" wo="0.1370661540479713" />
-        <nuclide name="Ni61" wo="0.006057615154415727" />
-        <nuclide name="Ni62" wo="0.01963045531316453" />
-        <nuclide name="Ni64" wo="0.005160721957533462" />
-    </material>
-    <material id="10006" name="Zircaloy 4">
-        <temperature>300</temperature>
-        <density units="g/cc" value="6.55" />
-        <nuclide name="O16" wo="0.0012494965182849112" />
-        <nuclide name="O17" wo="5.034817150887735e-07" />
-        <nuclide name="Cr50" wo="4.1736864731106146e-05" />
-        <nuclide name="Cr52" wo="0.0008369936242576807" />
-        <nuclide name="Cr53" wo="9.673586881507429e-05" />
-        <nuclide name="Cr54" wo="2.4533642196138756e-05" />
-        <nuclide name="Fe54" wo="0.00011855672274761877" />
-        <nuclide name="Fe56" wo="0.001929932104229657" />
-        <nuclide name="Fe57" wo="4.536774095388075e-05" />
-        <nuclide name="Fe58" wo="6.143432068843669e-06" />
-        <nuclide name="Zr90" wo="0.49750307249921255" />
-        <nuclide name="Zr91" wo="0.10970127796055709" />
-        <nuclide name="Zr92" wo="0.16952409354767467" />
-        <nuclide name="Zr94" wo="0.17553856942304608" />
-        <nuclide name="Zr96" wo="0.02888298656950975" />
-        <nuclide name="Sn112" wo="0.0001325869644430062" />
-        <nuclide name="Sn114" wo="9.182449637587617e-05" />
-        <nuclide name="Sn115" wo="4.771905922545867e-05" />
-        <nuclide name="Sn116" wo="0.002058423153629443" />
-        <nuclide name="Sn117" wo="0.0010966473429083066" />
-        <nuclide name="Sn118" wo="0.0034879812938438245" />
-        <nuclide name="Sn119" wo="0.001247577110245757" />
-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10007" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
-        <nuclide name="P31" wo="0.00025" />
-        <nuclide name="S32" wo="0.00023692152702311576" />
-        <nuclide name="S33" wo="1.924704844422474e-06" />
-        <nuclide name="S34" wo="1.1112880999711348e-05" />
-        <nuclide name="S36" wo="4.088713275043879e-08" />
-        <nuclide name="Si28" wo="0.0036749406913165338" />
-        <nuclide name="Si29" wo="0.00019327001171376318" />
-        <nuclide name="Si30" wo="0.0001317892969697033" />
-        <nuclide name="Ni58" wo="0.005039827898909675" />
-        <nuclide name="Ni60" wo="0.002008197216956016" />
-        <nuclide name="Ni61" wo="8.875193135010345e-05" />
-        <nuclide name="Ni62" wo="0.00028761167190610265" />
-        <nuclide name="Ni64" wo="7.561128087810308e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006341263666702117" />
-        <nuclide name="Mo92" wo="0.0008769932056639445" />
-        <nuclide name="Mo94" wo="0.0005619573981472699" />
-        <nuclide name="Mo95" wo="0.0009812790231824658" />
-        <nuclide name="Mo96" wo="0.0010415835207694215" />
-        <nuclide name="Mo97" wo="0.0006048497176301975" />
-        <nuclide name="Mo98" wo="0.00154921076793649" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.506648724403529e-06" />
-        <nuclide name="B11" wo="2.449335127559647e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10008" name="Fuel 1.6%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.9992419999999993" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10009" name="Fuel 2.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.9992420000000004" name="O16" />
-        <nuclide ao="0.0007580000000000002" name="O17" />
-        <nuclide ao="0.00019522327124383906" name="U234" />
-        <nuclide ao="0.024298776982208985" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10010" name="Fuel 3.1%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.9992420000000022" name="O16" />
-        <nuclide ao="0.0007580000000000009" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-    <material id="10011" name="Fuel 3.2%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.34115" />
-        <nuclide ao="1.9992419999999995" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00025991006602092703" name="U234" />
-        <nuclide ao="0.03235012244921097" name="U235" />
-        <nuclide ao="0.9673899674847681" name="U238" />
-    </material>
-    <material id="10012" name="Fuel 3.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.35917" />
-        <nuclide ao="1.999241999999999" name="O16" />
-        <nuclide ao="0.0007579999999999997" name="O17" />
-        <nuclide ao="0.0002770142199967032" name="U234" />
-        <nuclide ao="0.03447901835531245" name="U235" />
-        <nuclide ao="0.9652439674246908" name="U238" />
-    </material>
-    <material id="10013" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.013479369482225239" name="B10" />
-        <nuclide ao="0.054735873774104264" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

2x2-periodic/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="2x2-periodic" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>42.83456 42.83456</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

2x2-periodic/settings.xml

@@ -1,16 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10</particles>
-        <batches>2</batches>
-        <inactive>1</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-21.41728 -21.41728 192.5 21.41728 21.41728 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-</settings>

2x2-periodic/tallies.xml

@@ -1,11 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="10000" name="dummy distribcell tally">
-        <filter bins="10053" type="distribcell" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="dummy distribcell tally">
-        <filter bins="10061" type="distribcell" />
-        <scores>fission</scores>
-    </tally>
-</tallies>

2x2-reflector/build-depleted.py

@@ -1,141 +0,0 @@
-from collections import OrderedDict, defaultdict
-import copy
-import os
-
-import numpy as np
-import openmc
-import opendeplete
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create "dummy" inputs to export distribcell paths for burnable cells
-
-# Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-# Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-32.12592, -32.12592, 192.5]
-upper_right = [32.12592, 32.12592, 197.5]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-# Create OpenMC "settings.xml" file
-settings_file = openmc.Settings()
-settings_file.batches = 2
-settings_file.inactive = 1
-settings_file.particles = 10
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-settings_file.export_to_xml()
-
-#  Create OpenMC "tallies.xml" file
-tallies = openmc.Tallies()
-fuel_cells = openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-# Instantiate a "dummy" distribcell tally for each cell we wish to deplete
-for cell in fuel_cells:
-    tally = openmc.Tally(name='dummy distribcell tally')
-    distribcell_filter = openmc.DistribcellFilter([cell.id])
-    tally.filters = [distribcell_filter]
-    tally.scores = ['fission']
-    tallies.append(tally)
-
-tallies.export_to_xml()
-
-# Run OpenMC to generate summary.h5 file
-openmc.run()
-
-# Open "summary.h5" file
-su = openmc.Summary('summary.h5')
-fuel_cells = su.openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-
-#### Setup OpenDeplete Materials wrapper
-
-materials = opendeplete.Materials()
-materials.temperature = OrderedDict()
-materials.sab = OrderedDict()
-materials.initial_density = OrderedDict()
-materials.burn = OrderedDict()
-materials.cross_sections = os.environ["OPENMC_CROSS_SECTIONS"]
-
-# Extract cell materials, temperatures and sab
-for cell in su.openmc_geometry.get_all_material_cells():
-    materials.burn[cell.name] = 'fuel' in cell.fill.name.lower()
-    materials.temperature[cell.name] = cell.temperature[0]
-    if len(cell.fill._sab) > 0:
-        materials.sab[cell.name] = cell.fill._sab[0]
-
-# Extract initial fuel nuclide densities in units of at/cc
-for cell in fuel_cells:
-    densities = cell.fill.get_nuclide_atom_densities()
-    materials.initial_density[cell.fill.name] = OrderedDict()
-
-    # Convert atom densities from at/b-cm to at/cc
-    for nuclide in densities:
-        materials.initial_density[cell.fill.name][nuclide.name] = \
-            densities[nuclide][1] * 1e24
-
-# Determine the maximum material ID
-all_mats = su.openmc_geometry.get_all_materials()
-max_material_id = 0
-for material in all_mats:
-    max_material_id = max(max_material_id, material.id)
-
-# FIXME: Automatically extract info needed to calculate burnable cell volumes
-# Fuel rod geometric parameters
-radius = 0.39218
-height = 5.
-
-# Use defaultdict since OpenDeplete assumes volumes specified for all cells
-volumes = defaultdict(lambda: 1)
-
-# Assign distribmats for each material
-for cell in fuel_cells:
-    new_materials = []
-    num_instances = len(cell.distribcell_paths)
-
-    for i in range(num_instances):
-        new_material = copy.deepcopy(cell.fill)
-        new_material.id = max_material_id + 1
-        max_material_id += 1
-        new_materials.append(new_material)
-
-        # Store volume of burnable fuel rods cells
-        volumes[new_material.id] =  np.pi * radius**2 * height
-
-    cell.fill = new_materials
-
-# Create dt vector for 1 month with 15 day timesteps
-dt1 = 15*24*60*60  # 15 days
-dt2 = 1.*30*24*60*60  # 1 months
-N = np.floor(dt2/dt1)
-dt = np.repeat([dt1], N)
-
-# Create settings variable
-settings = opendeplete.Settings()
-
-settings.openmc_call = ["mpirun", "openmc"]
-settings.particles = 120000
-settings.batches = 30
-settings.inactive = 20
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [17*3, 17*3, 1]
-
-settings.power = 2.337e15 * ((17.*17.*2.) / 1.5**2)  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'depleted'
-
-op = opendeplete.Operator()
-op.geometry_fill(su.openmc_geometry, volumes, materials, settings)
-
-# Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrate(op, opendeplete.ce_cm_c1)

2x2-reflector/build-fresh.py

@@ -1,146 +0,0 @@
-"""Creates a 2D 2x2 assembly colorset with a water reflector."""
-
-import os
-import shutil
-
-import numpy as np
-import openmc
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-
-#### Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-32.12592, -32.12592, 192.5]
-upper_right = [32.12592, 32.12592, 197.5]
-lat_width = (np.array(upper_right) - np.array(lower_left))
-lat_width[:2] /= 3.
-
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-plot.width = [64.25184, 64.25184]
-plot.origin = [0., 0., 195.]
-plot.color = 'mat'
-plot.filename = '2x2-reflector'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [34, 34, 1]
-mesh.lower_left = [lower_left[0], lower_left[1] + lat_width[1], lower_left[2]]
-mesh.width = np.array(lat_width)
-mesh.width[:2] /= 17.
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()
-
-
-#### Move all XML files to 'fresh' directory
-
-if not os.path.exists('fresh'):
-    os.makedirs('fresh')
-    
-shutil.move('materials.xml', 'fresh/materials.xml')
-shutil.move('geometry.xml', 'fresh/geometry.xml')
-shutil.move('settings.xml', 'fresh/settings.xml')
-shutil.move('tallies.xml', 'fresh/tallies.xml')
-shutil.move('plots.xml', 'fresh/plots.xml')

2x2-reflector/build-xml.py

@@ -1,299 +0,0 @@
-"""Creates a 2D 2x2 assembly colorset with a water reflector."""
-
-import numpy as np
-
-import opencg
-import openmc
-import openmc.opencg_compatible as opencg_compatible
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenCG model.
-
-    This method extracts the fuel assembly and wraps it in an OpenCG Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenCG Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenCG Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get all OpenCG Universes
-    all_univ = beavrs.main_universe.get_all_universes()
-
-    # Iterate over all Universes
-    fuel_assembly = None
-    for univ_id, univ in all_univ.items():
-        if univ.name == assembly_name:
-            fuel_assembly = univ
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = opencg.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = opencg.XPlane(x0=root_cell.fill.min_x, boundary='reflective')
-        max_x = opencg.XPlane(x0=root_cell.fill.max_x, boundary='reflective')
-        min_y = opencg.YPlane(y0=root_cell.fill.min_y, boundary='reflective')
-        max_y = opencg.YPlane(y0=root_cell.fill.max_y, boundary='reflective')
-        max_z = opencg.ZPlane(z0=197.5, boundary='reflective')
-        min_z = opencg.ZPlane(z0=192.5, boundary='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = opencg.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = opencg.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-def build_reflector(assembly1_name, assembly2_name):
-    """Build a 2x2 fuel assembly geometry with a water reflector on the
-    bottom and right.
-
-    This routine puts reflective boundary conditions along min x, max y and z
-    and vacuum boundary conditions along the max x and min y boundaries.
-
-    Parameters
-    ----------
-    assembly1_name : str
-        The BEAVRS fuel assembly to place in the bottom right and top left
-    assembly2_name : str
-        The BEAVRS fuel assembly to place in the bottom left and top right
-
-    Returns
-    -------
-    opencg.Geometry
-        A 2x2 fuel assembly and reflector OpenCG Geometry
-
-    """
-
-    fuel_assembly1 = find_assembly(assembly1_name, wrap_geometry=False)
-    fuel_assembly2 = find_assembly(assembly2_name, wrap_geometry=False)
-
-    # Find the water material
-    all_cells = beavrs.main_universe.get_all_cells()
-    for cell_uuid, cell in all_cells.items():
-        if cell.type == 'material' and cell.fill.name == 'water':
-            water = cell.fill
-
-    # Create a Cell/Universe around the first fuel assembly
-    fuel_cell1 = opencg.Cell(name='assm1 cell')
-    fuel_cell1.fill = fuel_assembly1
-    fuel_univ1 = opencg.Universe(name='assm1 universe')
-    fuel_univ1.add_cell(fuel_cell1)
-
-    # Create a Cell/Universe around the second fuel assembly
-    fuel_cell2 = opencg.Cell(name='assm2 cell')
-    fuel_cell2.fill = fuel_assembly2
-    fuel_univ2 = opencg.Universe(name='assm2 universe')
-    fuel_univ2.add_cell(fuel_cell2)
-
-    # Create a Cell/Universe with water
-    water_cell = opencg.Cell(name='water cell', fill=water)
-    water_univ = opencg.Universe(name='water universe')
-    water_univ.add_cell(water_cell)
-
-    # Create a 3x3 lattice two fuel assemblies surrounded by a water reflector
-    reflector_lattice = opencg.Lattice(name='reflector')
-    lat_width = fuel_assembly1.max_x - fuel_assembly1.min_x
-    reflector_lattice.width = [lat_width, lat_width, 1000.]
-    reflector_lattice.dimension = [3, 3, 1]
-    reflector_lattice.offset = [0., 0., 0.]
-    reflector_lattice.universes = [[fuel_univ1, fuel_univ2, water_univ],
-                                   [fuel_univ2, fuel_univ1, water_univ],
-                                   [water_univ, water_univ, water_univ]]
-
-    # Create a Geometry around the reflected lattice
-    root_cell = opencg.Cell(name='root cell')
-    root_cell.fill = reflector_lattice
-
-    # Make mixed reflective / vacuum boundaries
-    min_x = opencg.XPlane(x0=root_cell.fill.min_x, boundary='reflective')
-    max_x = opencg.XPlane(x0=root_cell.fill.max_x, boundary='vacuum')
-    min_y = opencg.YPlane(y0=root_cell.fill.min_y, boundary='vacuum')
-    max_y = opencg.YPlane(y0=root_cell.fill.max_y, boundary='reflective')
-    min_z = opencg.ZPlane(z0=192.5, boundary='reflective')
-    max_z = opencg.ZPlane(z0=197.5, boundary='reflective')
-
-    # Add boundaries to the root Cell
-    root_cell.add_surface(surface=min_x, halfspace=+1)
-    root_cell.add_surface(surface=max_x, halfspace=-1)
-    root_cell.add_surface(surface=min_y, halfspace=+1)
-    root_cell.add_surface(surface=max_y, halfspace=-1)
-    root_cell.add_surface(surface=min_z, halfspace=+1)
-    root_cell.add_surface(surface=max_z, halfspace=-1)
-
-    # Create a root Universe for this fuel assembly
-    root_univ = opencg.Universe(universe_id=0, name='root universe')
-    root_univ.add_cell(root_cell)
-
-    # Create an OpenCG Geometry for this fuel assembly
-    reflector = opencg.Geometry()
-    reflector.root_universe = root_univ
-
-    return reflector
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS(nndc_xs=True)
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel assemblies of interest from BEAVRS model
-reflector = build_reflector('Fuel 1.6% enr instr no BAs',
-                            'Fuel 3.1% enr instr 20')
-openmc_geometry = opencg_compatible.get_openmc_geometry(reflector)
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = reflector.bounds[:3]
-upper_right = reflector.bounds[3:]
-
-lat_width = (np.array(upper_right) - np.array(lower_left))
-lat_width[:2] /= 3.
-
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.ptables = True
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-bounds = reflector.bounds
-plot.width = [reflector.max_x - reflector.min_x,
-              reflector.max_y - reflector.min_y]
-plot.origin = [bounds[0] + (bounds[3] - bounds[0]) / 2.,
-               bounds[1] + (bounds[4] - bounds[1]) / 2.,
-               bounds[2] + (bounds[5] - bounds[2]) / 2.]
-plot.color = 'mat'
-plot.filename = '2x2-reflector'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [34, 34, 1]
-mesh.lower_left = [lower_left[0], lower_left[1] + lat_width[1], lower_left[2]]
-mesh.width = np.array(lat_width)
-mesh.width[:2] /= 17.
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()

2x2-reflector/depleted/geometry.xml

@@ -1,244 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" temperature="300.0" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" temperature="300.0" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" temperature="300.0" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" temperature="300.0" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" temperature="300.0" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" temperature="293.6" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" temperature="300.0" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" temperature="293.6" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" temperature="300.0" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" temperature="300.0" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" temperature="300.0" universe="10007" />
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-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" temperature="300.0" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" temperature="300.0" universe="10008" />
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-    <cell id="10063" material="10006" name="Fuel rod active region - 3.1% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10010" />
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-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" temperature="300.0" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" temperature="300.0" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" temperature="300.0" universe="10014" />
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-    <cell id="10100" material="10016" name="Fuel rod - 3.1% enr axial 1: SS SPN" region="-10038 10000" temperature="300.0" universe="10018" />
-    <cell fill="10007" id="10101" name="Fuel rod - 3.1% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10018" />
-    <cell fill="10010" id="10102" name="Fuel rod - 3.1% enr axial 3: Fuel rod active region - 3.1% enr" region="-10040 10039" universe="10018" />
-    <cell fill="10013" id="10103" name="Fuel rod - 3.1% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10018" />
-    <cell fill="10007" id="10104" name="Fuel rod - 3.1% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10018" />
-    <cell id="10105" material="10014" name="Fuel rod - 3.1% enr axial 6: Borated Water" region="-10004 10042" temperature="300.0" universe="10018" />
-    <cell id="10106" material="10016" name="Fuel rod - 3.1% enr axial 7: SS SPN" region="-10005 10004" temperature="300.0" universe="10018" />
-    <cell id="10107" material="10014" name="Fuel rod - 3.1% enr axial top: Borated Water" region="10005" temperature="300.0" universe="10018" />
-    <cell fill="10018" id="10108" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 3.1% enr" region="-10036" universe="10019" />
-    <cell fill="10005" id="10109" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10019" />
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-    <cell id="10135" material="10014" name="Empty GT above the dashpot radial 0: Borated Water" region="-10043" temperature="300.0" universe="10025" />
-    <cell id="10136" material="10006" name="Empty GT above the dashpot radial 1: Zircaloy 4" region="10043 -10044" temperature="300.0" universe="10025" />
-    <cell id="10137" material="10014" name="Empty GT above the dashpot radial outer: Borated Water" region="10044" temperature="300.0" universe="10025" />
-    <cell id="10138" material="10014" name="Empty Guide Tube axial 0: Borated Water" region="-10000" temperature="300.0" universe="10026" />
-    <cell id="10139" material="10015" name="Empty Guide Tube axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10026" />
-    <cell fill="10024" id="10140" name="Empty Guide Tube axial 2: Empty GT below the dashpot" region="-10048 10047" universe="10026" />
-    <cell fill="10025" id="10141" name="Empty Guide Tube axial 3: Empty GT above the dashpot" region="-10049 10048" universe="10026" />
-    <cell id="10142" material="10015" name="Empty Guide Tube axial 4: Water SPN" region="-10005 10049" temperature="293.6" universe="10026" />
-    <cell id="10143" material="10014" name="Empty Guide Tube axial top: Borated Water" region="10005" temperature="300.0" universe="10026" />
-    <cell fill="10026" id="10144" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial 0: Empty Guide Tube" region="-10044" universe="10027" />
-    <cell fill="10005" id="10145" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10027" />
-    <cell id="10146" material="10014" name="Empty Guide Tube in Center Position axial 0: Borated Water" region="-10000" temperature="300.0" universe="10028" />
-    <cell id="10147" material="10015" name="Empty Guide Tube in Center Position axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10028" />
-    <cell fill="10025" id="10148" name="Empty Guide Tube in Center Position axial 2: Empty GT above the dashpot" region="-10049 10047" universe="10028" />
-    <cell id="10149" material="10015" name="Empty Guide Tube in Center Position axial 3: Water SPN" region="-10005 10049" temperature="293.6" universe="10028" />
-    <cell id="10150" material="10014" name="Empty Guide Tube in Center Position axial top: Borated Water" region="10005" temperature="300.0" universe="10028" />
-    <cell fill="10028" id="10151" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial 0: Empty Guide Tube in Ce" region="-10044" universe="10029" />
-    <cell fill="10005" id="10152" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial outer: Grids axial univer" region="10044" universe="10029" />
-    <cell id="10153" material="10000" name="Instrument tube thimble radial 0: Air" region="-10050" temperature="300.0" universe="10030" />
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-    <cell id="10157" material="10006" name="Instrument tube thimble support plane radial 1: Zircaloy 4" region="10050 -10051" temperature="300.0" universe="10031" />
-    <cell id="10158" material="10015" name="Instrument tube thimble support plane radial outer: Water SPN" region="10051" temperature="293.6" universe="10031" />
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-    <cell fill="10031" id="10160" name="Instrument tube axial stack axial 1: Instrument tube thimble support plane" region="-10038 10000" universe="10032" />
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-    <cell id="10162" material="10015" name="Instrument tube axial stack axial 3: Water SPN" region="-10005 10004" temperature="293.6" universe="10032" />
-    <cell id="10163" material="10014" name="Instrument tube axial stack axial top: Borated Water" region="10005" temperature="300.0" universe="10032" />
-    <cell fill="10032" id="10164" name="(Instrument tube axial stack) wrapped by ((Empty Guide Tube in Center Position) wrapped by (Grids axial" region="-10051" universe="10033" />
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-    <cell id="10167" material="10014" name="BPRA rod lower/upper fitting radial outer: Borated Water" region="10057" temperature="300.0" universe="10034" />
-    <cell id="10168" material="10000" name="BPRA rod active poison radial 0: Air" region="-10052" temperature="300.0" universe="10035" />
-    <cell id="10169" material="10001" name="BPRA rod active poison radial 1: SS304" region="10052 -10053" temperature="300.0" universe="10035" />
-    <cell id="10170" material="10000" name="BPRA rod active poison radial 2: Air" region="10053 -10054" temperature="300.0" universe="10035" />
-    <cell id="10171" material="10013" name="BPRA rod active poison radial 3: Borosilicate Glass" region="10054 -10055" temperature="300.0" universe="10035" />
-    <cell id="10172" material="10000" name="BPRA rod active poison radial 4: Air" region="10055 -10056" temperature="300.0" universe="10035" />
-    <cell id="10173" material="10001" name="BPRA rod active poison radial 5: SS304" region="10056 -10057" temperature="300.0" universe="10035" />
-    <cell id="10174" material="10014" name="BPRA rod active poison radial outer: Borated Water" region="10057" temperature="300.0" universe="10035" />
-    <cell id="10175" material="10000" name="BPRA rod plenum radial 0: Air" region="-10052" temperature="300.0" universe="10036" />
-    <cell id="10176" material="10001" name="BPRA rod plenum radial 1: SS304" region="10052 -10053" temperature="300.0" universe="10036" />
-    <cell id="10177" material="10000" name="BPRA rod plenum radial 2: Air" region="10053 -10056" temperature="300.0" universe="10036" />
-    <cell id="10178" material="10001" name="BPRA rod plenum radial 3: SS304" region="10056 -10057" temperature="300.0" universe="10036" />
-    <cell id="10179" material="10014" name="BPRA rod plenum radial outer: Borated Water" region="10057" temperature="300.0" universe="10036" />
-    <cell id="10180" material="10014" name="BPRA rod axial 0: Borated Water" region="-10000" temperature="300.0" universe="10037" />
-    <cell id="10181" material="10015" name="BPRA rod axial 1: Water SPN" region="-10003 10000" temperature="293.6" universe="10037" />
-    <cell id="10182" material="10014" name="BPRA rod axial 2: Borated Water" region="-10058 10003" temperature="300.0" universe="10037" />
-    <cell fill="10034" id="10183" name="BPRA rod axial 3: BPRA rod lower/upper fitting" region="-10059 10058" universe="10037" />
-    <cell fill="10035" id="10184" name="BPRA rod axial 4: BPRA rod active poison" region="-10060 10059" universe="10037" />
-    <cell fill="10036" id="10185" name="BPRA rod axial 5: BPRA rod plenum" region="-10061 10060" universe="10037" />
-    <cell fill="10034" id="10186" name="BPRA rod axial 6: BPRA rod lower/upper fitting" region="-10062 10061" universe="10037" />
-    <cell id="10187" material="10014" name="BPRA rod axial top: Borated Water" region="10062" temperature="300.0" universe="10037" />
-    <cell fill="10037" id="10188" name="(BPRA rod) wrapped by ((Empty Guide Tube) wrapped by (Grids axial universe)) radial 0: BPRA rod" region="-10057" universe="10038" />
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-    <cell id="11275" material="10014" name="water cell" temperature="300.0" universe="10767" />
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-10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 10015 </universes>
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-    <lattice id="10419" name="Fuel 3.1% enr instr 20">
-        <pitch>1.25984 1.25984</pitch>
-        <dimension>17 17</dimension>
-        <lower_left>-10.70864 -10.70864</lower_left>
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2x2-reflector/depleted/settings.xml

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2x2-reflector/fresh/geometry.xml

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2x2-reflector/fresh/materials.xml

@@ -1,267 +0,0 @@
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-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10008" name="Fuel 1.6%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.9992419999999993" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10009" name="Fuel 2.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.9992420000000004" name="O16" />
-        <nuclide ao="0.0007580000000000002" name="O17" />
-        <nuclide ao="0.00019522327124383906" name="U234" />
-        <nuclide ao="0.024298776982208985" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10010" name="Fuel 3.1%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.9992420000000022" name="O16" />
-        <nuclide ao="0.0007580000000000009" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-    <material id="10011" name="Fuel 3.2%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.34115" />
-        <nuclide ao="1.9992419999999995" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00025991006602092703" name="U234" />
-        <nuclide ao="0.03235012244921097" name="U235" />
-        <nuclide ao="0.9673899674847681" name="U238" />
-    </material>
-    <material id="10012" name="Fuel 3.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.35917" />
-        <nuclide ao="1.999241999999999" name="O16" />
-        <nuclide ao="0.0007579999999999997" name="O17" />
-        <nuclide ao="0.0002770142199967032" name="U234" />
-        <nuclide ao="0.03447901835531245" name="U235" />
-        <nuclide ao="0.9652439674246908" name="U238" />
-    </material>
-    <material id="10013" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.013479369482225239" name="B10" />
-        <nuclide ao="0.054735873774104264" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

2x2-reflector/fresh/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="2x2-reflector" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>64.25184 64.25184</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

2x2-reflector/fresh/settings.xml

@@ -1,18 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>10</batches>
-        <inactive>5</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-32.12592 -32.12592 192.5 32.12592 32.12592 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

2x2-reflector/fresh/tallies.xml

@@ -1,299 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <!--assembly mesh-->
-    <mesh id="10000" type="regular">
-        <dimension>34 34 1</dimension>
-        <lower_left>-32.12592 -10.70864 192.5</lower_left>
-        <width>1.25984 1.25984 5.0</width>
-    </mesh>
-    <tally id="10000" name="fission rates">
-        <filter bins="10000" type="mesh" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="u-238 capture">
-        <filter bins="10000" type="mesh" />
-        <nuclides>U238</nuclides>
-        <scores>absorption fission</scores>
-    </tally>
-    <tally id="10006">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10007">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10008">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
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-    <tally id="10009">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10010">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10011">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10016">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10017">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10018">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
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-    <tally id="10019">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
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-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10020">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10021">
-        <filter bins="10061" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10161">
-        <filter bins="10000 10001 10004 10005 10006 10008 10010 10013 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10050">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10165">
-        <filter bins="10000 10001 10004 10005 10006 10008 10010 10013 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10058">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10061">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10062">
-        <filter bins="10000 10001 10004" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10090">
-        <filter bins="10001 10004 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission total</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10094">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10098">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10101">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10102">
-        <filter bins="10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10081">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10083">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10085">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10086">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10158">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10166">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10169">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10170">
-        <filter bins="10010 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10121">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10123">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10125">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10126">
-        <filter bins="10013" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10162">
-        <filter bins="10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10150">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10153">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10154">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

2x2-reflector/geometry.py

@@ -1,161 +0,0 @@
-import openmc
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenMC model.
-
-    This method extracts the fuel assembly and wraps it in an OpenMC Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenMC Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenMC Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get OpenMC Lattices for the fuel assembly
-    fuel_assembly = \
-        beavrs.openmc_geometry.get_lattices_by_name(assembly_name)[0]
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = openmc.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = openmc.XPlane(x0=-10.70864, boundary_type='reflective')
-        max_x = openmc.XPlane(x0=+-10.70864, boundary_type='reflective')
-        min_y = openmc.YPlane(y0=-10.70864, boundary_type='reflective')
-        max_y = openmc.YPlane(y0=+-10.70864, boundary_type='reflective')
-        max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
-        min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = openmc.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = openmc.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-def build_reflector(assembly1_name, assembly2_name):
-    """Build a 2x2 fuel assembly geometry with a water reflector on the
-    bottom and right.
-
-    This routine puts reflective boundary conditions along min x, max y and z
-    and vacuum boundary conditions along the max x and min y boundaries.
-
-    Parameters
-    ----------
-    assembly1_name : str
-        The BEAVRS fuel assembly to place in the bottom right and top left
-    assembly2_name : str
-        The BEAVRS fuel assembly to place in the bottom left and top right
-
-    Returns
-    -------
-    openmc.Geometry
-        A 2x2 fuel assembly and reflector OpenMC Geometry
-
-    """
-
-    fuel_assembly1 = find_assembly(assembly1_name, wrap_geometry=False)
-    fuel_assembly2 = find_assembly(assembly2_name, wrap_geometry=False)
-
-    # Find the water material
-    all_cells = beavrs.main_universe.get_all_cells()
-    for cell_uuid, cell in all_cells.items():
-        if cell.fill_type == 'material' and cell.fill.name == 'Borated Water':
-            water = cell.fill
-
-    # Create a Cell/Universe around the first fuel assembly
-    fuel_cell1 = openmc.Cell(name='assm1 cell')
-    fuel_cell1.fill = fuel_assembly1
-    fuel_univ1 = openmc.Universe(name='assm1 universe')
-    fuel_univ1.add_cell(fuel_cell1)
-
-    # Create a Cell/Universe around the second fuel assembly
-    fuel_cell2 = openmc.Cell(name='assm2 cell')
-    fuel_cell2.fill = fuel_assembly2
-    fuel_univ2 = openmc.Universe(name='assm2 universe')
-    fuel_univ2.add_cell(fuel_cell2)
-
-    # Create a Cell/Universe with water
-    water_cell = openmc.Cell(name='water cell', fill=water)
-    water_univ = openmc.Universe(name='water universe')
-    water_univ.add_cell(water_cell)
-
-    # Create a 3x3 lattice two fuel assemblies surrounded by a water reflector
-    reflector_lattice = openmc.RectLattice(name='reflector')
-    reflector_lattice.lower_left = [-32.12592, -32.12592, -500.]
-    reflector_lattice.pitch = [21.41728, 21.41728, 1000.]
-    reflector_lattice.universes = [[[fuel_univ1, fuel_univ2, water_univ],
-                                   [fuel_univ2, fuel_univ1, water_univ],
-                                   [water_univ, water_univ, water_univ]]]
-
-    # Create a Geometry around the reflected lattice
-    root_cell = openmc.Cell(name='root cell')
-    root_cell.fill = reflector_lattice
-
-    # Make mixed reflective / vacuum boundaries
-    min_x = openmc.XPlane(x0=-32.12592, boundary_type='reflective')
-    max_x = openmc.XPlane(x0=+32.12592, boundary_type='vacuum')
-    min_y = openmc.YPlane(y0=-32.12592, boundary_type='vacuum')
-    max_y = openmc.YPlane(y0=+32.12592, boundary_type='reflective')
-    min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
-    max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
-
-    # Add boundaries to the root Cell
-    root_cell.add_surface(surface=min_x, halfspace=+1)
-    root_cell.add_surface(surface=max_x, halfspace=-1)
-    root_cell.add_surface(surface=min_y, halfspace=+1)
-    root_cell.add_surface(surface=max_y, halfspace=-1)
-    root_cell.add_surface(surface=min_z, halfspace=+1)
-    root_cell.add_surface(surface=max_z, halfspace=-1)
-
-    # Create a root Universe for this fuel assembly
-    root_univ = openmc.Universe(universe_id=0, name='root universe')
-    root_univ.add_cell(root_cell)
-
-    # Create an OpenMC Geometry for this fuel assembly
-    reflector = openmc.Geometry()
-    reflector.root_universe = root_univ
-
-    return reflector
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS()
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel assemblies of interest from BEAVRS model
-openmc_geometry = build_reflector('Fuel 1.6% enr instr no BAs',
-                                  'Fuel 3.1% enr instr 20')

2x2-reflector/geometry.xml

@@ -1,244 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" universe="10007" />
-    <cell id="10053" material="10008" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" universe="10008" />
-    <cell id="10061" material="10010" name="Fuel rod active region - 3.1% enr radial 0: Fuel 3.1%" region="-10034" universe="10010" />
-    <cell id="10062" material="10004" name="Fuel rod active region - 3.1% enr radial 1: Helium" region="10034 -10035" universe="10010" />
-    <cell id="10063" material="10006" name="Fuel rod active region - 3.1% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10010" />
-    <cell id="10064" material="10014" name="Fuel rod active region - 3.1% enr radial outer: Borated Water" region="10036" universe="10010" />
-    <cell id="10073" material="10005" name="Fuel rod plenum radial 0: Inconel 718" region="-10037" universe="10013" />
-    <cell id="10074" material="10004" name="Fuel rod plenum radial 1: Helium" region="10037 -10035" universe="10013" />
-    <cell id="10075" material="10006" name="Fuel rod plenum radial 2: Zircaloy 4" region="10035 -10036" universe="10013" />
-    <cell id="10076" material="10014" name="Fuel rod plenum radial outer: Borated Water" region="10036" universe="10013" />
-    <cell id="10077" material="10014" name="Fuel rod - 1.6% enr axial 0: Borated Water" region="-10000" universe="10014" />
-    <cell id="10078" material="10016" name="Fuel rod - 1.6% enr axial 1: SS SPN" region="-10038 10000" universe="10014" />
-    <cell fill="10007" id="10079" name="Fuel rod - 1.6% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10014" />
-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" universe="10014" />
-    <cell fill="10014" id="10086" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 1.6% enr" region="-10036" universe="10015" />
-    <cell fill="10005" id="10087" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10015" />
-    <cell id="10099" material="10014" name="Fuel rod - 3.1% enr axial 0: Borated Water" region="-10000" universe="10018" />
-    <cell id="10100" material="10016" name="Fuel rod - 3.1% enr axial 1: SS SPN" region="-10038 10000" universe="10018" />
-    <cell fill="10007" id="10101" name="Fuel rod - 3.1% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10018" />
-    <cell fill="10010" id="10102" name="Fuel rod - 3.1% enr axial 3: Fuel rod active region - 3.1% enr" region="-10040 10039" universe="10018" />
-    <cell fill="10013" id="10103" name="Fuel rod - 3.1% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10018" />
-    <cell fill="10007" id="10104" name="Fuel rod - 3.1% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10018" />
-    <cell id="10105" material="10014" name="Fuel rod - 3.1% enr axial 6: Borated Water" region="-10004 10042" universe="10018" />
-    <cell id="10106" material="10016" name="Fuel rod - 3.1% enr axial 7: SS SPN" region="-10005 10004" universe="10018" />
-    <cell id="10107" material="10014" name="Fuel rod - 3.1% enr axial top: Borated Water" region="10005" universe="10018" />
-    <cell fill="10018" id="10108" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 3.1% enr" region="-10036" universe="10019" />
-    <cell fill="10005" id="10109" name="(Fuel rod - 3.1% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10019" />
-    <cell id="10132" material="10014" name="Empty GT below the dashpot radial 0: Borated Water" region="-10045" universe="10024" />
-    <cell id="10133" material="10006" name="Empty GT below the dashpot radial 1: Zircaloy 4" region="10045 -10046" universe="10024" />
-    <cell id="10134" material="10014" name="Empty GT below the dashpot radial outer: Borated Water" region="10046" universe="10024" />
-    <cell id="10135" material="10014" name="Empty GT above the dashpot radial 0: Borated Water" region="-10043" universe="10025" />
-    <cell id="10136" material="10006" name="Empty GT above the dashpot radial 1: Zircaloy 4" region="10043 -10044" universe="10025" />
-    <cell id="10137" material="10014" name="Empty GT above the dashpot radial outer: Borated Water" region="10044" universe="10025" />
-    <cell id="10138" material="10014" name="Empty Guide Tube axial 0: Borated Water" region="-10000" universe="10026" />
-    <cell id="10139" material="10015" name="Empty Guide Tube axial 1: Water SPN" region="-10047 10000" universe="10026" />
-    <cell fill="10024" id="10140" name="Empty Guide Tube axial 2: Empty GT below the dashpot" region="-10048 10047" universe="10026" />
-    <cell fill="10025" id="10141" name="Empty Guide Tube axial 3: Empty GT above the dashpot" region="-10049 10048" universe="10026" />
-    <cell id="10142" material="10015" name="Empty Guide Tube axial 4: Water SPN" region="-10005 10049" universe="10026" />
-    <cell id="10143" material="10014" name="Empty Guide Tube axial top: Borated Water" region="10005" universe="10026" />
-    <cell fill="10026" id="10144" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial 0: Empty Guide Tube" region="-10044" universe="10027" />
-    <cell fill="10005" id="10145" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10027" />
-    <cell id="10146" material="10014" name="Empty Guide Tube in Center Position axial 0: Borated Water" region="-10000" universe="10028" />
-    <cell id="10147" material="10015" name="Empty Guide Tube in Center Position axial 1: Water SPN" region="-10047 10000" universe="10028" />
-    <cell fill="10025" id="10148" name="Empty Guide Tube in Center Position axial 2: Empty GT above the dashpot" region="-10049 10047" universe="10028" />
-    <cell id="10149" material="10015" name="Empty Guide Tube in Center Position axial 3: Water SPN" region="-10005 10049" universe="10028" />
-    <cell id="10150" material="10014" name="Empty Guide Tube in Center Position axial top: Borated Water" region="10005" universe="10028" />
-    <cell fill="10028" id="10151" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial 0: Empty Guide Tube in Center Position" region="-10044" universe="10029" />
-    <cell fill="10005" id="10152" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10029" />
-    <cell id="10153" material="10000" name="Instrument tube thimble radial 0: Air" region="-10050" universe="10030" />
-    <cell id="10154" material="10006" name="Instrument tube thimble radial 1: Zircaloy 4" region="10050 -10051" universe="10030" />
-    <cell id="10155" material="10014" name="Instrument tube thimble radial outer: Borated Water" region="10051" universe="10030" />
-    <cell id="10156" material="10000" name="Instrument tube thimble support plane radial 0: Air" region="-10050" universe="10031" />
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2x2-reflector/materials.xml

@@ -1,267 +0,0 @@
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-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10007" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
-        <nuclide name="P31" wo="0.00025" />
-        <nuclide name="S32" wo="0.00023692152702311576" />
-        <nuclide name="S33" wo="1.924704844422474e-06" />
-        <nuclide name="S34" wo="1.1112880999711348e-05" />
-        <nuclide name="S36" wo="4.088713275043879e-08" />
-        <nuclide name="Si28" wo="0.0036749406913165338" />
-        <nuclide name="Si29" wo="0.00019327001171376318" />
-        <nuclide name="Si30" wo="0.0001317892969697033" />
-        <nuclide name="Ni58" wo="0.005039827898909675" />
-        <nuclide name="Ni60" wo="0.002008197216956016" />
-        <nuclide name="Ni61" wo="8.875193135010345e-05" />
-        <nuclide name="Ni62" wo="0.00028761167190610265" />
-        <nuclide name="Ni64" wo="7.561128087810308e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006341263666702117" />
-        <nuclide name="Mo92" wo="0.0008769932056639445" />
-        <nuclide name="Mo94" wo="0.0005619573981472699" />
-        <nuclide name="Mo95" wo="0.0009812790231824658" />
-        <nuclide name="Mo96" wo="0.0010415835207694215" />
-        <nuclide name="Mo97" wo="0.0006048497176301975" />
-        <nuclide name="Mo98" wo="0.00154921076793649" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.506648724403529e-06" />
-        <nuclide name="B11" wo="2.449335127559647e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10008" name="Fuel 1.6%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.9992419999999993" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10009" name="Fuel 2.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.9992420000000004" name="O16" />
-        <nuclide ao="0.0007580000000000002" name="O17" />
-        <nuclide ao="0.00019522327124383906" name="U234" />
-        <nuclide ao="0.024298776982208985" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10010" name="Fuel 3.1%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.9992420000000022" name="O16" />
-        <nuclide ao="0.0007580000000000009" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-    <material id="10011" name="Fuel 3.2%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.34115" />
-        <nuclide ao="1.9992419999999995" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00025991006602092703" name="U234" />
-        <nuclide ao="0.03235012244921097" name="U235" />
-        <nuclide ao="0.9673899674847681" name="U238" />
-    </material>
-    <material id="10012" name="Fuel 3.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.35917" />
-        <nuclide ao="1.999241999999999" name="O16" />
-        <nuclide ao="0.0007579999999999997" name="O17" />
-        <nuclide ao="0.0002770142199967032" name="U234" />
-        <nuclide ao="0.03447901835531245" name="U235" />
-        <nuclide ao="0.9652439674246908" name="U238" />
-    </material>
-    <material id="10013" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.013479369482225239" name="B10" />
-        <nuclide ao="0.054735873774104264" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

2x2-reflector/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="2x2-reflector" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>64.25184 64.25184</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

2x2-reflector/settings.xml

@@ -1,16 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10</particles>
-        <batches>2</batches>
-        <inactive>1</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-32.12592 -32.12592 192.5 32.12592 32.12592 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-</settings>

2x2-reflector/tallies.xml

@@ -1,11 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="10000" name="dummy distribcell tally">
-        <filter bins="10053" type="distribcell" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="dummy distribcell tally">
-        <filter bins="10061" type="distribcell" />
-        <scores>fission</scores>
-    </tally>
-</tallies>

README.md

@@ -1,64 +1,37 @@
-ECP Benchmarks
-==============
+ExaSMR Benchmarks
+=================
 
-This repository contains benchmarks for performance profiling of the OpenMC
-and Shift Monte Carlo codes for ECP. Each directory contains a ``build-xml.py``
+This repository contains benchmarks for performance profiling of the OpenMC and
+Shift Monte Carlo codes for the ECP ExaSMR project. Each directory contains a
 Python script which uses the OpenMC Python API to create XML input files for
-OpenMC. The Python scripts and the XML files are included in this repository.
-Each benchmark is derived from a subset (*e.g.*, fuel pins, assemblies) of the
-full-core BEAVRS model with fresh UO2 fuel at HZP conditions. Each benchmark is
-modeled in 2D with reflective boundary conditions along the axial dimension.
+OpenMC.
 
 Model Descriptions
 ------------------
 
-**fuel-pin**  
-A single fuel pin with reflective boundary conditions (*i.e.*, an infinitely
-repeating array of fuel pins). The default configuration is the BEAVRS fuel pin
-with fresh 1.6% enriched UO2 fuel, but the script can be toggled to 2.4% or
-3.1% enriched fuel.
-
-**assembly**  
-A single fuel assembly with reflective boundary conditions (*i.e.*, an infinitely
-repeating lattice of fuel assemblies). The default configuration is the BEAVRS
-assembly with fresh 1.6% enriched UO2 fuel with 24 water-filled control rod
-guide tubes and a central air-filled instrument tube. However, the script can
-be toggled to use any of the 20+ fuel assemblies in the BEAVRS model.
-
-**2x2-periodic**  
-A 2x2 fuel assembly colorset with periodic boundary conditions (*i.e.*, an
-infinitely repeating lattice of the 2x2 assembly colorset). The default
-configuration includes the BEAVRS assembly with fresh 1.6% enriched UO2 fuel
-with 24 water-filled control rod guide tubes and a central air-filled
-instrument tube, along with a 3.1% enriched fuel assembly with 20 burnable
-poisons, four control rod guide tubes and a central instrument tube. However,
-the script may be toggled to use any pair of the 20+ fuel assemblies in the
-BEAVRS model.
-
-**2x2-reflector**  
-A 2x2 fuel assembly colorset surrounded by a water reflector. Reflective
-boundary conditions are used on the top and left boundaries (adjacent to the
-assemblies) and vacuum boundary conditions are used on the bottom and right
-boundaries (adjacent to the reflector).  The default configuration includes
-the BEAVRS assembly with fresh 1.6% enriched UO2 fuel with 24 water-filled
-control rod guide tubes and a central air-filled instrument tube, along with a
-3.1% enriched fuel assembly with 20 burnable poisons, four control rod guide
-tubes and a central instrument tube. However, the script may be toggled to use
-any pair of the 20+ fuel assemblies in the BEAVRS model.
+<dl>
+    <dt>smr</dt>
+    <dd>A 3D Small Modular Reactor (SMR) model that roughly mimics the design of
+    the NuScale reactor. The reactor core has 37 fuel assemblies that alternate
+    between 3.1% enriched and 2.4% enriched UO2 fuel. The center fuel assembly
+    has 1.6% enriched UO2 fuel. Where possible, we have attempted to use the
+    same parameters for the fuel assemblies and fuel rods as those specified in
+    the NuScale <a
+    href="https://www.nrc.gov/reactors/new-reactors/design-cert/nuscale.html">design
+    submittal</a> to the Nuclear Regulatory Commission (NRC), for example: 264
+    fuel rods per assembly, 24 guide tubes per assembly, 1 instrument tube per
+    assembly, five spacer grids per assembly, fuel rod pitch of 0.496 in, and an
+    active fuel length of 200 cm. Many of the details of the actual NuScale fuel
+    assembly design are redacted from the design submittal because they are
+    export controlled/proprietary information. The purpose of our model is not
+    to be an exact replica of the NuScale model; rather, it is intended to
+    capture most of the physical complexities that are involved in modeling a
+    full reactor core and to provide a suitable model for carrying out full core
+    performance tests on the testbed architectures.</dd>
+</dl>
 
 Dependencies
 ------------
 
-These scripts depend on the following Python packages:
-
-* mit-crpg/openmc (develop branch)
-* mit-crpg/PWR_benchmarks
-
-Of particular note, The Python ``beavrs`` package must be installed from the
-mit-crpg/PWR_benchmarks repository. This package may be installed with
-``distutils`` as follows:
-
-```bash
-cd PWR_benchmarks/BEAVRS/openmc/inputs
-python setup.py install
-```
+To generate models using the scripts in this package, you must use a recent
+version of OpenMC's Python API.

assembly/build-depleted.py

@@ -1,140 +0,0 @@
-from collections import OrderedDict, defaultdict
-import copy
-import os
-
-import numpy as np
-import openmc
-import opendeplete
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create "dummy" inputs to export distribcell paths for burnable cells
-
-# Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-# Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-10.70864, -10.70864, +192.5]
-upper_right = [+10.70864, +10.70864, +197.5]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-# Create OpenMC "settings.xml" file
-settings_file = openmc.Settings()
-settings_file.batches = 2
-settings_file.inactive = 1
-settings_file.particles = 10
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-settings_file.export_to_xml()
-
-#  Create OpenMC "tallies.xml" file
-tallies = openmc.Tallies()
-fuel_cells = openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-# Instantiate a "dummy" distribcell tally for each cell we wish to deplete
-for cell in fuel_cells:
-    tally = openmc.Tally(name='dummy distribcell tally')
-    distribcell_filter = openmc.DistribcellFilter([cell.id])
-    tally.filters = [distribcell_filter]
-    tally.scores = ['fission']
-    tallies.append(tally)
-
-tallies.export_to_xml()
-
-# Run OpenMC to generate summary.h5 file
-openmc.run()
-
-# Open "summary.h5" file
-su = openmc.Summary('summary.h5')
-fuel_cells = su.openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-#### Setup OpenDeplete Materials wrapper
-
-materials = opendeplete.Materials()
-materials.temperature = OrderedDict()
-materials.sab = OrderedDict()
-materials.initial_density = OrderedDict()
-materials.burn = OrderedDict()
-materials.cross_sections = os.environ["OPENMC_CROSS_SECTIONS"]
-
-# Extract cell materials, temperatures and sab
-for cell in su.openmc_geometry.get_all_material_cells():
-    materials.burn[cell.name] = 'fuel' in cell.fill.name.lower()
-    materials.temperature[cell.name] = cell.temperature[0]
-    if len(cell.fill._sab) > 0:
-        materials.sab[cell.name] = cell.fill._sab[0]
-
-# Extract initial fuel nuclide densities in units of at/cc
-for cell in fuel_cells:
-    densities = cell.fill.get_nuclide_atom_densities()
-    materials.initial_density[cell.fill.name] = OrderedDict()
-
-    # Convert atom densities from at/b-cm to at/cc
-    for nuclide in densities:
-        materials.initial_density[cell.fill.name][nuclide.name] = \
-            densities[nuclide][1] * 1e24
-
-# Determine the maximum material ID
-all_mats = su.openmc_geometry.get_all_materials()
-max_material_id = 0
-for material in all_mats:
-    max_material_id = max(max_material_id, material.id)
-
-# FIXME: Automatically extract info needed to calculate burnable cell volumes
-# Fuel rod geometric parameters
-radius = 0.39218
-height = 5.
-
-# Use defaultdict since OpenDeplete assumes volumes specified for all cells
-volumes = defaultdict(lambda: 1)
-
-# Assign distribmats for each material
-for cell in fuel_cells:
-    new_materials = []
-    num_instances = len(cell.distribcell_paths)
-
-    for i in range(num_instances):
-        new_material = copy.deepcopy(cell.fill)
-        new_material.id = max_material_id + 1
-        max_material_id += 1
-        new_materials.append(new_material)
-
-        # Store volume of burnable fuel rods cells
-        volumes[new_material.id] =  np.pi * radius**2 * height
-
-    cell.fill = new_materials
-
-# Create dt vector for 1 month with 15 day timesteps
-dt1 = 15*24*60*60  # 15 days
-dt2 = 1.*30*24*60*60  # 1 months
-N = np.floor(dt2/dt1)
-dt = np.repeat([dt1], N)
-
-# Create settings variable
-settings = opendeplete.Settings()
-
-settings.openmc_call = ["mpirun", "openmc"]
-settings.particles = 30000
-settings.batches = 20
-settings.inactive = 10
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [17, 17, 1]
-
-settings.power = 2.337e15 * (17.**2 / 1.5**2)  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'depleted'
-
-op = opendeplete.Operator()
-op.geometry_fill(su.openmc_geometry, volumes, materials, settings)
-
-# Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrate(op, opendeplete.ce_cm_c1)

assembly/build-fresh.py

@@ -1,143 +0,0 @@
-"""Creates a 2D fuel assembly with reflective BCs."""
-
-import os
-import shutil
-
-import numpy as np
-import openmc
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-
-#### Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-10.70864, -10.70864, +192.5]
-upper_right = [+10.70864, +10.70864, +197.5]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-plot.width = [10.70864*2, 10.70864*2]
-plot.origin = [0., 0., 195.]
-plot.color = 'mat'
-plot.filename = 'assembly'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [17, 17, 1]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= 17
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()
-
-
-#### Move all XML files to 'fresh' directory
-
-if not os.path.exists('fresh'):
-    os.makedirs('fresh')
-    
-shutil.move('materials.xml', 'fresh/materials.xml')
-shutil.move('geometry.xml', 'fresh/geometry.xml')
-shutil.move('settings.xml', 'fresh/settings.xml')
-shutil.move('tallies.xml', 'fresh/tallies.xml')
-shutil.move('plots.xml', 'fresh/plots.xml')

assembly/build-xml.py

@@ -1,207 +0,0 @@
-"""Creates a 2D fuel assembly with reflective BCs."""
-
-import numpy as np
-
-import opencg
-import openmc
-import openmc.opencg_compatible as opencg_compatible
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenCG model.
-
-    This method extracts the fuel assembly and wraps it in an OpenCG Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenCG Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenCG Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get all OpenCG Universes
-    all_univ = beavrs.main_universe.get_all_universes()
-
-    # Iterate over all Universes
-    fuel_assembly = None
-    for univ_id, univ in all_univ.items():
-        if univ.name == assembly_name:
-            fuel_assembly = univ
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = opencg.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = opencg.XPlane(x0=root_cell.fill.min_x, boundary='reflective')
-        max_x = opencg.XPlane(x0=root_cell.fill.max_x, boundary='reflective')
-        min_y = opencg.YPlane(y0=root_cell.fill.min_y, boundary='reflective')
-        max_y = opencg.YPlane(y0=root_cell.fill.max_y, boundary='reflective')
-        max_z = opencg.ZPlane(z0=197.5, boundary='reflective')
-        min_z = opencg.ZPlane(z0=192.5, boundary='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = opencg.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = opencg.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS(nndc_xs=True)
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel assembly of interest from BEAVRS model
-assm_name = 'Fuel 1.6% enr instr no BAs'
-fuel_assembly = find_assembly(assm_name)
-openmc_geometry = opencg_compatible.get_openmc_geometry(fuel_assembly)
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = fuel_assembly.bounds[:3]
-upper_right = fuel_assembly.bounds[3:]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.ptables = True
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-bounds = fuel_assembly.bounds
-plot.width = [fuel_assembly.max_x - fuel_assembly.min_x,
-              fuel_assembly.max_y - fuel_assembly.min_y]
-plot.origin = [bounds[0] + (bounds[3] - bounds[0]) / 2.,
-               bounds[1] + (bounds[4] - bounds[1]) / 2.,
-               bounds[2] + (bounds[5] - bounds[2]) / 2.]
-plot.color = 'mat'
-plot.filename = 'assembly'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = openmc_geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [17, 17, 1]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= 17
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()

assembly/depleted/geometry.xml

@@ -1,159 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" temperature="300.0" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" temperature="300.0" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" temperature="300.0" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" temperature="300.0" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" temperature="300.0" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" temperature="293.6" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" temperature="300.0" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" temperature="300.0" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" temperature="300.0" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" temperature="293.6" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" temperature="300.0" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" temperature="300.0" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" temperature="300.0" universe="10007" />
-    <cell id="10053" material="10017 10018 10019 10020 10021 10022 10023 10024 10025 10026 10027 10028 10029 10030 10031 10032 10033 10034 10035 10036 10037 10038 10039 10040 10041 10042 10043 10044 10045 10046 10047 10048 10049 10050 10051 10052 10053 10054 10055 10056 10057 10058 10059 10060 10061 10062 10063 10064 10065 10066 10067 10068 10069 10070 10071 10072 10073 10074 10075 10076 10077 10078 10079 10080 10081 10082 10083 10084 10085 10086 10087 10088 10089 10090 10091 10092 10093 10094 10095 10096 10097 10098 10099 10100 10101 10102 10103 10104 10105 10106 10107 10108 10109 10110 10111 10112 10113 10114 10115 10116 10117 10118 10119 10120 10121 10122 10123 10124 10125 10126 10127 10128 10129 10130 10131 10132 10133 10134 10135 10136 10137 10138 10139 10140 10141 10142 10143 10144 10145 10146 10147 10148 10149 10150 10151 10152 10153 10154 10155 10156 10157 10158 10159 10160 10161 10162 10163 10164 10165 10166 10167 10168 10169 10170 10171 10172 10173 10174 10175 10176 10177 10178 10179 10180 10181 10182 10183 10184 10185 10186 10187 10188 10189 10190 10191 10192 10193 10194 10195 10196 10197 10198 10199 10200 10201 10202 10203 10204 10205 10206 10207 10208 10209 10210 10211 10212 10213 10214 10215 10216 10217 10218 10219 10220 10221 10222 10223 10224 10225 10226 10227 10228 10229 10230 10231 10232 10233 10234 10235 10236 10237 10238 10239 10240 10241 10242 10243 10244 10245 10246 10247 10248 10249 10250 10251 10252 10253 10254 10255 10256 10257 10258 10259 10260 10261 10262 10263 10264 10265 10266 10267 10268 10269 10270 10271 10272 10273 10274 10275 10276 10277 10278 10279 10280" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" temperature="300.0" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" temperature="300.0" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" temperature="300.0" universe="10008" />
-    <cell id="10073" material="10005" name="Fuel rod plenum radial 0: Inconel 718" region="-10037" temperature="300.0" universe="10013" />
-    <cell id="10074" material="10004" name="Fuel rod plenum radial 1: Helium" region="10037 -10035" temperature="300.0" universe="10013" />
-    <cell id="10075" material="10006" name="Fuel rod plenum radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10013" />
-    <cell id="10076" material="10014" name="Fuel rod plenum radial outer: Borated Water" region="10036" temperature="300.0" universe="10013" />
-    <cell id="10077" material="10014" name="Fuel rod - 1.6% enr axial 0: Borated Water" region="-10000" temperature="300.0" universe="10014" />
-    <cell id="10078" material="10016" name="Fuel rod - 1.6% enr axial 1: SS SPN" region="-10038 10000" temperature="300.0" universe="10014" />
-    <cell fill="10007" id="10079" name="Fuel rod - 1.6% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10014" />
-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" temperature="300.0" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" temperature="300.0" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" temperature="300.0" universe="10014" />
-    <cell fill="10014" id="10086" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 1.6% enr" region="-10036" universe="10015" />
-    <cell fill="10005" id="10087" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10015" />
-    <cell id="10132" material="10014" name="Empty GT below the dashpot radial 0: Borated Water" region="-10045" temperature="300.0" universe="10024" />
-    <cell id="10133" material="10006" name="Empty GT below the dashpot radial 1: Zircaloy 4" region="10045 -10046" temperature="300.0" universe="10024" />
-    <cell id="10134" material="10014" name="Empty GT below the dashpot radial outer: Borated Water" region="10046" temperature="300.0" universe="10024" />
-    <cell id="10135" material="10014" name="Empty GT above the dashpot radial 0: Borated Water" region="-10043" temperature="300.0" universe="10025" />
-    <cell id="10136" material="10006" name="Empty GT above the dashpot radial 1: Zircaloy 4" region="10043 -10044" temperature="300.0" universe="10025" />
-    <cell id="10137" material="10014" name="Empty GT above the dashpot radial outer: Borated Water" region="10044" temperature="300.0" universe="10025" />
-    <cell id="10138" material="10014" name="Empty Guide Tube axial 0: Borated Water" region="-10000" temperature="300.0" universe="10026" />
-    <cell id="10139" material="10015" name="Empty Guide Tube axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10026" />
-    <cell fill="10024" id="10140" name="Empty Guide Tube axial 2: Empty GT below the dashpot" region="-10048 10047" universe="10026" />
-    <cell fill="10025" id="10141" name="Empty Guide Tube axial 3: Empty GT above the dashpot" region="-10049 10048" universe="10026" />
-    <cell id="10142" material="10015" name="Empty Guide Tube axial 4: Water SPN" region="-10005 10049" temperature="293.6" universe="10026" />
-    <cell id="10143" material="10014" name="Empty Guide Tube axial top: Borated Water" region="10005" temperature="300.0" universe="10026" />
-    <cell fill="10026" id="10144" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial 0: Empty Guide Tube" region="-10044" universe="10027" />
-    <cell fill="10005" id="10145" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10027" />
-    <cell id="10146" material="10014" name="Empty Guide Tube in Center Position axial 0: Borated Water" region="-10000" temperature="300.0" universe="10028" />
-    <cell id="10147" material="10015" name="Empty Guide Tube in Center Position axial 1: Water SPN" region="-10047 10000" temperature="293.6" universe="10028" />
-    <cell fill="10025" id="10148" name="Empty Guide Tube in Center Position axial 2: Empty GT above the dashpot" region="-10049 10047" universe="10028" />
-    <cell id="10149" material="10015" name="Empty Guide Tube in Center Position axial 3: Water SPN" region="-10005 10049" temperature="293.6" universe="10028" />
-    <cell id="10150" material="10014" name="Empty Guide Tube in Center Position axial top: Borated Water" region="10005" temperature="300.0" universe="10028" />
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assembly/depleted/settings.xml

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assembly/depleted/tallies.xml

@@ -1,8 +0,0 @@
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assembly/fresh/geometry.xml

@@ -1,159 +0,0 @@
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assembly/fresh/materials.xml

@@ -1,267 +0,0 @@
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-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

assembly/fresh/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="assembly" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>21.41728 21.41728</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

assembly/fresh/settings.xml

@@ -1,18 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>10</batches>
-        <inactive>5</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-10.70864 -10.70864 192.5 10.70864 10.70864 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

assembly/fresh/tallies.xml

@@ -1,198 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <!--assembly mesh-->
-    <mesh id="10000" type="regular">
-        <dimension>17 17 1</dimension>
-        <lower_left>-10.70864 -10.70864 192.5</lower_left>
-        <width>1.25984 1.25984 5.0</width>
-    </mesh>
-    <tally id="10000" name="fission rates">
-        <filter bins="10000" type="mesh" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="u-238 capture">
-        <filter bins="10000" type="mesh" />
-        <nuclides>U238</nuclides>
-        <scores>absorption fission</scores>
-    </tally>
-    <tally id="10006">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10007">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10008">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10009">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10010">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10011">
-        <filter bins="10053" type="distribcell" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10111">
-        <filter bins="10000 10004 10005 10006 10008 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10040">
-        <filter bins="10000 10004 10005" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 He3 He4 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10115">
-        <filter bins="10000 10004 10005 10006 10008 10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
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-    <tally id="10048">
-        <filter bins="10000 10004 10005" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 He3 He4 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10051">
-        <filter bins="10000 10004 10005" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 He3 He4 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10052">
-        <filter bins="10000 10004 10005" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 He3 He4 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10068">
-        <filter bins="10004 10005 10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>He3 He4 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission total</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10059">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10061">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
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-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10063">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10064">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10108">
-        <filter bins="10008 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission total</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10116">
-        <filter bins="10008 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10119">
-        <filter bins="10008 10016" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10120">
-        <filter bins="10008 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10112">
-        <filter bins="10014 10015 10016" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10100">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10103">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10104">
-        <filter bins="10014 10015" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

assembly/geometry.py

@@ -1,70 +0,0 @@
-import openmc
-from beavrs.builder import BEAVRS
-
-
-def find_assembly(assembly_name, wrap_geometry=True):
-    """Find a fuel assembly with some string name in the BEAVRS OpenMC model.
-
-    This method extracts the fuel assembly and wraps it in an OpenMC Geometry.
-    The returned geometry has reflective boundary conditions along all
-    boundaries. The z-axis is bounded between z=200 and z=210 cm.
-
-    Parameters
-    ----------
-    assembly_name : str
-        The name of the fuel assembly lattice
-    wrap_geometry : bool
-        If false, the fuel assembly Lattice is returned. If true, the fuel
-        assembly Lattice is wrapped in an OpenMC Geometry and returned (default).
-
-    Returns
-    -------
-    fuel_assembly
-        The OpenMC Lattice or Geometry for the assembly or None if not found
-
-    """
-
-    # Get OpenMC Lattices for the fuel assembly
-    fuel_assembly = \
-        beavrs.openmc_geometry.get_lattices_by_name(assembly_name)[0]
-
-    # Wrap lattice in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Create a root Cell
-        root_cell = openmc.Cell(name='root cell')
-        root_cell.fill = fuel_assembly
-
-        # Make mixed reflective / vacuum boundaries
-        min_x = openmc.XPlane(x0=-10.70864, boundary_type='reflective')
-        max_x = openmc.XPlane(x0=+10.70864, boundary_type='reflective')
-        min_y = openmc.YPlane(y0=-10.70864, boundary_type='reflective')
-        max_y = openmc.YPlane(y0=+10.70864, boundary_type='reflective')
-        max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
-        min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-        root_cell.add_surface(surface=min_z, halfspace=+1)
-        root_cell.add_surface(surface=max_z, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = openmc.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_assembly = openmc.Geometry()
-        fuel_assembly.root_universe = root_univ
-
-    return fuel_assembly
-
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS()
-
-# Extract fuel assembly of interest from BEAVRS model
-assm_name = 'Fuel 1.6% enr instr no BAs'
-openmc_geometry = find_assembly(assm_name)

assembly/geometry.xml

@@ -1,159 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10001" material="10014" name="Intermediate grid pincell radial 0: Borated Water" region="10010 -10011 10012 -10013" universe="10001" />
-    <cell id="10002" material="10006" name="Intermediate grid pincell radial outer: Zircaloy 4" region="~(10010 -10011 10012 -10013)" universe="10001" />
-    <cell id="10003" material="10014" name="Top/Bottom grid pincell radial 0: Borated Water" region="10006 -10007 10008 -10009" universe="10002" />
-    <cell id="10004" material="10005" name="Top/Bottom grid pincell radial outer: Inconel 718" region="~(10006 -10007 10008 -10009)" universe="10002" />
-    <cell id="10009" material="10014" name="Grids axial universe axial 0: Borated Water" region="-10000" universe="10005" />
-    <cell id="10010" material="10015" name="Grids axial universe axial 1: Water SPN" region="-10003 10000" universe="10005" />
-    <cell id="10011" material="10014" name="Grids axial universe axial 2: Borated Water" region="-10018 10003" universe="10005" />
-    <cell fill="10002" id="10012" name="Grids axial universe axial 3: Top/Bottom grid pincell" region="-10019 10018" universe="10005" />
-    <cell id="10013" material="10014" name="Grids axial universe axial 4: Borated Water" region="-10020 10019" universe="10005" />
-    <cell fill="10001" id="10014" name="Grids axial universe axial 5: Intermediate grid pincell" region="-10021 10020" universe="10005" />
-    <cell id="10015" material="10014" name="Grids axial universe axial 6: Borated Water" region="-10022 10021" universe="10005" />
-    <cell fill="10001" id="10016" name="Grids axial universe axial 7: Intermediate grid pincell" region="-10023 10022" universe="10005" />
-    <cell id="10017" material="10014" name="Grids axial universe axial 8: Borated Water" region="-10024 10023" universe="10005" />
-    <cell fill="10001" id="10018" name="Grids axial universe axial 9: Intermediate grid pincell" region="-10025 10024" universe="10005" />
-    <cell id="10019" material="10014" name="Grids axial universe axial 10: Borated Water" region="-10026 10025" universe="10005" />
-    <cell fill="10001" id="10020" name="Grids axial universe axial 11: Intermediate grid pincell" region="-10027 10026" universe="10005" />
-    <cell id="10021" material="10014" name="Grids axial universe axial 12: Borated Water" region="-10028 10027" universe="10005" />
-    <cell fill="10001" id="10022" name="Grids axial universe axial 13: Intermediate grid pincell" region="-10029 10028" universe="10005" />
-    <cell id="10023" material="10014" name="Grids axial universe axial 14: Borated Water" region="-10030 10029" universe="10005" />
-    <cell fill="10001" id="10024" name="Grids axial universe axial 15: Intermediate grid pincell" region="-10031 10030" universe="10005" />
-    <cell id="10025" material="10014" name="Grids axial universe axial 16: Borated Water" region="-10032 10031" universe="10005" />
-    <cell fill="10002" id="10026" name="Grids axial universe axial 17: Top/Bottom grid pincell" region="-10033 10032" universe="10005" />
-    <cell id="10027" material="10014" name="Grids axial universe axial 18: Borated Water" region="-10004 10033" universe="10005" />
-    <cell id="10028" material="10015" name="Grids axial universe axial 19: Water SPN" region="-10005 10004" universe="10005" />
-    <cell id="10029" material="10014" name="Grids axial universe axial top: Borated Water" region="10005" universe="10005" />
-    <cell id="10051" material="10006" name="Fuel rod lower/upper fitting radial 0: Zircaloy 4" region="-10036" universe="10007" />
-    <cell id="10052" material="10014" name="Fuel rod lower/upper fitting radial outer: Borated Water" region="10036" universe="10007" />
-    <cell id="10053" material="10008" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" universe="10008" />
-    <cell id="10073" material="10005" name="Fuel rod plenum radial 0: Inconel 718" region="-10037" universe="10013" />
-    <cell id="10074" material="10004" name="Fuel rod plenum radial 1: Helium" region="10037 -10035" universe="10013" />
-    <cell id="10075" material="10006" name="Fuel rod plenum radial 2: Zircaloy 4" region="10035 -10036" universe="10013" />
-    <cell id="10076" material="10014" name="Fuel rod plenum radial outer: Borated Water" region="10036" universe="10013" />
-    <cell id="10077" material="10014" name="Fuel rod - 1.6% enr axial 0: Borated Water" region="-10000" universe="10014" />
-    <cell id="10078" material="10016" name="Fuel rod - 1.6% enr axial 1: SS SPN" region="-10038 10000" universe="10014" />
-    <cell fill="10007" id="10079" name="Fuel rod - 1.6% enr axial 2: Fuel rod lower/upper fitting" region="-10039 10038" universe="10014" />
-    <cell fill="10008" id="10080" name="Fuel rod - 1.6% enr axial 3: Fuel rod active region - 1.6% enr" region="-10040 10039" universe="10014" />
-    <cell fill="10013" id="10081" name="Fuel rod - 1.6% enr axial 4: Fuel rod plenum" region="-10041 10040" universe="10014" />
-    <cell fill="10007" id="10082" name="Fuel rod - 1.6% enr axial 5: Fuel rod lower/upper fitting" region="-10042 10041" universe="10014" />
-    <cell id="10083" material="10014" name="Fuel rod - 1.6% enr axial 6: Borated Water" region="-10004 10042" universe="10014" />
-    <cell id="10084" material="10016" name="Fuel rod - 1.6% enr axial 7: SS SPN" region="-10005 10004" universe="10014" />
-    <cell id="10085" material="10014" name="Fuel rod - 1.6% enr axial top: Borated Water" region="10005" universe="10014" />
-    <cell fill="10014" id="10086" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial 0: Fuel rod - 1.6% enr" region="-10036" universe="10015" />
-    <cell fill="10005" id="10087" name="(Fuel rod - 1.6% enr) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10036" universe="10015" />
-    <cell id="10132" material="10014" name="Empty GT below the dashpot radial 0: Borated Water" region="-10045" universe="10024" />
-    <cell id="10133" material="10006" name="Empty GT below the dashpot radial 1: Zircaloy 4" region="10045 -10046" universe="10024" />
-    <cell id="10134" material="10014" name="Empty GT below the dashpot radial outer: Borated Water" region="10046" universe="10024" />
-    <cell id="10135" material="10014" name="Empty GT above the dashpot radial 0: Borated Water" region="-10043" universe="10025" />
-    <cell id="10136" material="10006" name="Empty GT above the dashpot radial 1: Zircaloy 4" region="10043 -10044" universe="10025" />
-    <cell id="10137" material="10014" name="Empty GT above the dashpot radial outer: Borated Water" region="10044" universe="10025" />
-    <cell id="10138" material="10014" name="Empty Guide Tube axial 0: Borated Water" region="-10000" universe="10026" />
-    <cell id="10139" material="10015" name="Empty Guide Tube axial 1: Water SPN" region="-10047 10000" universe="10026" />
-    <cell fill="10024" id="10140" name="Empty Guide Tube axial 2: Empty GT below the dashpot" region="-10048 10047" universe="10026" />
-    <cell fill="10025" id="10141" name="Empty Guide Tube axial 3: Empty GT above the dashpot" region="-10049 10048" universe="10026" />
-    <cell id="10142" material="10015" name="Empty Guide Tube axial 4: Water SPN" region="-10005 10049" universe="10026" />
-    <cell id="10143" material="10014" name="Empty Guide Tube axial top: Borated Water" region="10005" universe="10026" />
-    <cell fill="10026" id="10144" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial 0: Empty Guide Tube" region="-10044" universe="10027" />
-    <cell fill="10005" id="10145" name="(Empty Guide Tube) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10027" />
-    <cell id="10146" material="10014" name="Empty Guide Tube in Center Position axial 0: Borated Water" region="-10000" universe="10028" />
-    <cell id="10147" material="10015" name="Empty Guide Tube in Center Position axial 1: Water SPN" region="-10047 10000" universe="10028" />
-    <cell fill="10025" id="10148" name="Empty Guide Tube in Center Position axial 2: Empty GT above the dashpot" region="-10049 10047" universe="10028" />
-    <cell id="10149" material="10015" name="Empty Guide Tube in Center Position axial 3: Water SPN" region="-10005 10049" universe="10028" />
-    <cell id="10150" material="10014" name="Empty Guide Tube in Center Position axial top: Borated Water" region="10005" universe="10028" />
-    <cell fill="10028" id="10151" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial 0: Empty Guide Tube in Center Position" region="-10044" universe="10029" />
-    <cell fill="10005" id="10152" name="(Empty Guide Tube in Center Position) wrapped by (Grids axial universe) radial outer: Grids axial universe" region="10044" universe="10029" />
-    <cell id="10153" material="10000" name="Instrument tube thimble radial 0: Air" region="-10050" universe="10030" />
-    <cell id="10154" material="10006" name="Instrument tube thimble radial 1: Zircaloy 4" region="10050 -10051" universe="10030" />
-    <cell id="10155" material="10014" name="Instrument tube thimble radial outer: Borated Water" region="10051" universe="10030" />
-    <cell id="10156" material="10000" name="Instrument tube thimble support plane radial 0: Air" region="-10050" universe="10031" />
-    <cell id="10157" material="10006" name="Instrument tube thimble support plane radial 1: Zircaloy 4" region="10050 -10051" universe="10031" />
-    <cell id="10158" material="10015" name="Instrument tube thimble support plane radial outer: Water SPN" region="10051" universe="10031" />
-    <cell fill="10030" id="10159" name="Instrument tube axial stack axial 0: Instrument tube thimble" region="-10000" universe="10032" />
-    <cell fill="10031" id="10160" name="Instrument tube axial stack axial 1: Instrument tube thimble support plane" region="-10038 10000" universe="10032" />
-    <cell fill="10030" id="10161" name="Instrument tube axial stack axial 2: Instrument tube thimble" region="-10004 10038" universe="10032" />
-    <cell id="10162" material="10015" name="Instrument tube axial stack axial 3: Water SPN" region="-10005 10004" universe="10032" />
-    <cell id="10163" material="10014" name="Instrument tube axial stack axial top: Borated Water" region="10005" universe="10032" />
-    <cell fill="10032" id="10164" name="(Instrument tube axial stack) wrapped by ((Empty Guide Tube in Center Position) wrapped by (Grids axial universe)) radial 0: Instrument tube axial stack" region="-10051" universe="10033" />
-    <cell fill="10029" id="10165" name="(Instrument tube axial stack) wrapped by ((Empty Guide Tube in Center Position) wrapped by (Grids axial universe)) radial outer: (Empty Guide Tube in Center Position) wrapped by (Grids axial universe)" region="10051" universe="10033" />
-    <cell fill="10065" id="11273" name="root cell" region="10149 -10150 10151 -10152 10154 -10153" universe="0" />
-    <lattice id="10065" name="Fuel 1.6% enr instr no BAs">
-        <pitch>1.25984 1.25984</pitch>
-        <dimension>17 17</dimension>
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assembly/materials.xml

@@ -1,267 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
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-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

assembly/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="assembly" id="10020" type="slice">
-        <origin>0.0 0.0 195.0</origin>
-        <width>21.41728 21.41728</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

assembly/settings.xml

@@ -1,16 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10</particles>
-        <batches>2</batches>
-        <inactive>1</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-10.70864 -10.70864 192.5 10.70864 10.70864 197.5</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-</settings>

assembly/tallies.xml

@@ -1,7 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="10000" name="dummy distribcell tally">
-        <filter bins="10053" type="distribcell" />
-        <scores>fission</scores>
-    </tally>
-</tallies>

pin-cell/build-depleted.py

@@ -1,140 +0,0 @@
-from collections import OrderedDict, defaultdict
-import copy
-import os
-
-import numpy as np
-import openmc
-import opendeplete
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create "dummy" inputs to export distribcell paths for burnable cells
-
-# Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-# Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-0.62992, -0.62992, -10.0]
-upper_right = [+0.62992, +0.62992, +10.0]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-# Create OpenMC "settings.xml" file
-settings_file = openmc.Settings()
-settings_file.batches = 2
-settings_file.inactive = 1
-settings_file.particles = 10
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-settings_file.export_to_xml()
-
-#  Create OpenMC "tallies.xml" file
-tallies = openmc.Tallies()
-fuel_cells = openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-# Instantiate a "dummy" distribcell tally for each cell we wish to deplete
-for cell in fuel_cells:
-    tally = openmc.Tally(name='dummy distribcell tally')
-    distribcell_filter = openmc.DistribcellFilter([cell.id])
-    tally.filters = [distribcell_filter]
-    tally.scores = ['fission']
-    tallies.append(tally)
-
-tallies.export_to_xml()
-
-# Run OpenMC to generate summary.h5 file
-openmc.run()
-
-# Open "summary.h5" file
-su = openmc.Summary('summary.h5')
-fuel_cells = su.openmc_geometry.get_cells_by_name(
-    name='enr radial 0: Fuel', case_sensitive=True)
-
-#### Setup OpenDeplete Materials wrapper
-
-materials = opendeplete.Materials()
-materials.temperature = OrderedDict()
-materials.sab = OrderedDict()
-materials.initial_density = OrderedDict()
-materials.burn = OrderedDict()
-materials.cross_sections = os.environ["OPENMC_CROSS_SECTIONS"]
-
-# Extract cell materials, temperatures and sab
-for cell in su.openmc_geometry.get_all_material_cells():
-    materials.burn[cell.name] = 'fuel' in cell.fill.name.lower()
-    materials.temperature[cell.name] = cell.temperature[0]
-    if len(cell.fill._sab) > 0:
-        materials.sab[cell.name] = cell.fill._sab[0]
-
-# Extract initial fuel nuclide densities in units of at/cc
-for cell in fuel_cells:
-    densities = cell.fill.get_nuclide_atom_densities()
-    materials.initial_density[cell.fill.name] = OrderedDict()
-
-    # Convert atom densities from at/b-cm to at/cc
-    for nuclide in densities:
-        materials.initial_density[cell.fill.name][nuclide.name] = \
-            densities[nuclide][1] * 1e24
-
-# Determine the maximum material ID
-all_mats = su.openmc_geometry.get_all_materials()
-max_material_id = 0
-for material in all_mats:
-    max_material_id = max(max_material_id, material.id)
-
-# FIXME: Automatically extract info needed to calculate burnable cell volumes
-# Fuel rod geometric parameters
-radius = 0.39218
-height = 5.
-
-# Use defaultdict since OpenDeplete assumes volumes specified for all cells
-volumes = defaultdict(lambda: 1)
-
-# Assign distribmats for each material
-for cell in fuel_cells:
-    new_materials = []
-    num_instances = len(cell.distribcell_paths)
-
-    for i in range(num_instances):
-        new_material = copy.deepcopy(cell.fill)
-        new_material.id = max_material_id + 1
-        max_material_id += 1
-        new_materials.append(new_material)
-
-        # Store volume of burnable fuel rods cells
-        volumes[new_material.id] =  np.pi * radius**2 * height
-
-    cell.fill = new_materials
-
-# Create dt vector for 1 month with 15 day timesteps
-dt1 = 15*24*60*60  # 15 days
-dt2 = 1.*30*24*60*60  # 1 months
-N = np.floor(dt2/dt1)
-dt = np.repeat([dt1], N)
-
-# Create settings variable
-settings = opendeplete.Settings()
-
-settings.openmc_call = ["mpirun", "openmc"]
-settings.particles = 10000
-settings.batches = 20
-settings.inactive = 10
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [1, 1, 1]
-
-settings.power = 2.337e15 * (1.**2 / 1.5**2)  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'depleted'
-
-op = opendeplete.Operator()
-op.geometry_fill(su.openmc_geometry, volumes, materials, settings)
-
-# Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrate(op, opendeplete.ce_cm_c1)

pin-cell/build-fresh.py

@@ -1,100 +0,0 @@
-"""Creates a 2D fuel pin with reflective BCs."""
-
-import os
-import shutil
-
-import numpy as np
-import openmc
-
-from geometry import beavrs, openmc_geometry
-
-
-#### Create OpenMC "materials.xml" file
-beavrs.write_openmc_materials()
-
-
-#### Create OpenMC "geometry.xml" file
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-0.62992, -0.62992, -10.0]
-upper_right = [+0.62992, +0.62992, +10.0]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-plot.width = [1.25984, 1.25984]
-plot.origin = [0., 0., np.inf]
-plot.color = 'mat'
-plot.filename = 'fuel-pin'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS library and "tallies.xml" file
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group MGXS library
-mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mgxs_lib.energy_groups = energy_groups
-mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mgxs_lib.domain_type = 'material'
-mgxs_lib.correction = None
-mgxs_lib.build_library()
-
-# Create a "tallies.xml" file for the MGXS Library
-tallies_file = openmc.Tallies()
-mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()
-
-
-#### Move all XML files to 'fresh' directory
-
-if not os.path.exists('fresh'):
-    os.makedirs('fresh')
-    
-shutil.move('materials.xml', 'fresh/materials.xml')
-shutil.move('geometry.xml', 'fresh/geometry.xml')
-shutil.move('settings.xml', 'fresh/settings.xml')
-shutil.move('tallies.xml', 'fresh/tallies.xml')
-shutil.move('plots.xml', 'fresh/plots.xml')

pin-cell/build-xml.py

@@ -1,164 +0,0 @@
-"""Creates a 2D fuel pin cell with reflective BCs."""
-
-import numpy as np
-
-import opencg
-import openmc
-import openmc.opencg_compatible as opencg_compatible
-from beavrs.builder import BEAVRS
-
-
-def find_pin(pin_name, wrap_geometry=True):
-    """Find a fuel pin with some string name in the BEAVRS OpenCG model.
-
-    This method extracts the pin cell and wraps it in an OpenCG Geometry.
-    The returned geometry has reflective boundary conditions along the x and y
-    boundaries. The z-axis left unbounded.
-
-    Parameters
-    ----------
-    pin_name : str
-        The name of the fuel pin universe
-    wrap_geometry : bool
-        If false, the pin cell Universe is returned. If true, the pin cell
-        Universe is wrapped in an OpenCG Geometry and returned (default).
-
-    Returns
-    -------
-    opencg.Universe
-        The OpenCG Universe or Geometry for this fuel pin or None if not found
-
-    """
-
-    # Get all OpenCG Universes
-    all_univ = beavrs.main_universe.get_all_universes()
-
-    # Iterate over all Universes
-    fuel_pin = None
-    for univ_id, univ in all_univ.items():
-        if univ._name == pin_name:
-            fuel_pin = univ
-
-    # Wrap pin cell Universe in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Make reflective boundaries
-        pin_pitch = 0.62992
-        min_x = opencg.XPlane(x0=-pin_pitch, boundary='reflective')
-        max_x = opencg.XPlane(x0=pin_pitch, boundary='reflective')
-        min_y = opencg.YPlane(y0=-pin_pitch, boundary='reflective')
-        max_y = opencg.YPlane(y0=pin_pitch, boundary='reflective')
-
-        # Create a root Cell
-        root_cell = opencg.Cell(name='root cell')
-        root_cell.fill = fuel_pin
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = opencg.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_pin = opencg.Geometry()
-        fuel_pin.root_universe = root_univ
-
-    return fuel_pin
-
-
-#### Create OpenMC "materials.xml" and "geometry.xml" files
-
-# User-specified enrichment of 1.6, 2.4 or 3.1 percent
-enrichment = 1.6
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS(nndc_xs=True)
-
-# Write all BEAVRS materials to materials.xml file
-beavrs.write_openmc_materials()
-
-# Extract fuel pin of interest from BEAVRS model
-pin_name = 'Fuel rod active region - {}% enr'.format(enrichment)
-pin_geometry = find_pin(pin_name)
-openmc_geometry = opencg_compatible.get_openmc_geometry(pin_geometry)
-openmc_geometry.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = True if multipole == 'y' else False
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = pin_geometry.bounds[:2] + [-10.]
-upper_right = pin_geometry.bounds[3:5] + [10.]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings_file = openmc.Settings()
-settings_file.batches = 10
-settings_file.inactive = 5
-settings_file.particles = 10000
-settings_file.ptables = True
-settings_file.output = {'tallies': False}
-settings_file.source = source
-settings_file.sourcepoint_write = False
-
-if multipole:
-    settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings_file.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-
-# Initialize the BEAVRS color mapping scheme
-beavrs.write_openmc_plots()
-
-# Create a plot colored by materials
-plot = openmc.Plot()
-bounds = pin_geometry.bounds
-plot.width = [pin_geometry.max_x - pin_geometry.min_x,
-              pin_geometry.max_y - pin_geometry.min_y]
-plot.origin = [bounds[0] + (bounds[3] - bounds[0]) / 2.,
-               bounds[1] + (bounds[4] - bounds[1]) / 2.,
-               bounds[2] + (bounds[5] - bounds[2]) / 2.]
-plot.color = 'mat'
-plot.filename = 'fuel-pin'
-plot.col_spec = beavrs.plots.colspec_mat
-plot.pixels = [1000, 1000]
-
-plot_file = openmc.Plots([plot])
-plot_file.export_to_xml()
-
-
-#### Create OpenMC MGXS library and "tallies.xml" file
-
-# CASMO 70-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([
-    0, 0.005, 0.01, 0.015, 0.02, 0.025, 0.03, 0.035, 0.042, 0.05, 0.058, 0.067,
-    0.08, 0.1, 0.14, 0.18, 0.22, 0.25, 0.28, 0.3, 0.32, 0.35, 0.4, 0.5, 0.625,
-    0.78, 0.85, 0.91, 0.95, 0.972, 0.996, 1.02, 1.045, 1.071, 1.097, 1.123,
-    1.15, 1.3, 1.5, 1.855, 2.1, 2.6, 3.3, 4., 9.877, 15.968, 27.7, 48.052,
-    75.501, 148.73, 367.26001, 906.90002, 1.4251e3, 2.2395e3, 3.5191e3, 5.53e3,
-    9.118e3, 15.03e3, 24.78e3, 40.85e3, 67.34e3, 111.e3, 183e3, 302.5e3, 500e3,
-    821e3, 1.353e6, 2.231e6, 3.679e6, 6.0655e6, 2e7])
-
-# Initialize a 70-group MGXS library
-mgxs_lib = openmc.mgxs.Library(openmc_geometry, by_nuclide=True)
-mgxs_lib.energy_groups = energy_groups
-mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mgxs_lib.domain_type = 'material'
-mgxs_lib.correction = None
-mgxs_lib.build_library()
-
-# Create a "tallies.xml" file for the MGXS Library
-tallies_file = openmc.Tallies()
-mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()

pin-cell/depleted/geometry.xml

@@ -1,15 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10053" material="10008" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" temperature="300.0" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" temperature="300.0" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" temperature="300.0" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" temperature="300.0" universe="10008" />
-    <cell fill="10008" id="11273" name="root cell" region="10149 -10150 10151 -10152" universe="0" />
-    <surface coeffs="0.0 0.0 0.39218" id="10034" name="Fuel pellet OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.40005" id="10035" name="Fuel clad IR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.4572" id="10036" name="Fuel clad OR" type="z-cylinder" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10149" type="x-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10150" type="x-plane" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10151" type="y-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10152" type="y-plane" />
-</geometry>

pin-cell/depleted/settings.xml

@@ -1,14 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>20</batches>
-        <inactive>10</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="box">
-            <parameters>-0.62992 -0.62992 -10.0 0.62992 0.62992 10.0</parameters>
-        </space>
-    </source>
-    <seed>7648980261882456387</seed>
-</settings>

pin-cell/depleted/tallies.xml

@@ -1,8 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="1">
-        <filter bins="10008" type="material" />
-        <nuclides>Sr90 Te122 Dy160 Xe126 Br79 Cd108 Xe132 Rb85 Sn123 Te120 Er166 U239 Sr86 Y90 Ru103 Ba135 Ni60 Sm153 Cs134 Xe131 Co59 Ga69 In115 Pu240 Pu238 Kr80 Ba136 Nb93 Mo97 Te132 Ce143 Eu153 Cd112 Ce140 Sb123 I131 Er168 Ho165 Mo94 Pd110 U240 Ru104 I127 Rh105 Ge73 Pm148 Ni64 Gd154 Se82 Zr92 Nd144 Dy158 U236 Pd108 Dy156 Er164 Kr83 U234 In113 La140 U235 Eu154 Ru105 Ce142 Ba133 Cu65 Np235 Ce141 U238 Fe58 Np236 Kr86 Cs133 Nd142 Zr90 Ge72 Pr141 Pd102 Mo100 Zn65 Sm150 Xe134 Ba130 Pm151 Tb159 Zn70 Zn68 Cs135 Ce144 Pd106 Ag109 Gd160 Ba134 Ge76 Cs137 Cd113 Mo99 Tm168 Zr96 Mo92 Ni62 Np238 Cd116 Rb87 Xe129 Te124 Xe128 Pu241 Sr88 Sr87 Sm149 Pd107 Nd146 Sn124 Tb160 Kr85 Dy164 Sb126 Gd156 As74 Pm147 Ni61 Sm147 Nd150 Cu63 Ce136 Nd148 Np239 Fe57 Zr95 Ni59 Sb121 Rb86 Y91 I135 Sn115 Xe135 Te128 Pu236 Ge70 Ag107 Sn112 Gd158 B11 Zr91 Np234 Ru102 Ba140 Dy161 Te126 I130 Se74 Se80 Xe130 Sr84 Mo96 Sn116 O17 Sn117 Nd145 Pd104 Sn118 Sn114 Sb124 Kr84 Zn67 Pu237 Ru98 Se78 Eu155 Np237 Se76 Mo95 Dy163 Gd157 Sm154 Cd111 Pm149 Eu152 B10 Eu157 Er170 Te123 Cd110 Rh103 Sn119 Pr142 Ga71 Pr143 Kr82 Ge74 Zn66 N15 Sm151 Pu239 Sn126 As75 Sn122 Sm152 Ag111 Sn125 U237 Mo98 La138 Ru101 Nd147 Sm148 Eu156 Cs136 Gd155 Ba132 Y89 Dy162 Pd105 Gd153 Er167 Nd143 Sr89 Xe133 Ce138 Nb95 Te130 Zr93 Ba138 Sn113 Gd152 Se79 Cd114 I129 Ru99 Zr94 Ba137 Te125 La139 Ru106 Se77 Sb125 Xe136 O16 Li7 Br81 Tm170 Ru100 N14 Tm169 Ce139 Sn120 Tc99 Zn64 Pu242 Eu151 Nb94</nuclides>
-        <scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
-    </tally>
-</tallies>

pin-cell/fresh/geometry.xml

@@ -1,15 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10053" material="10008" name="Fuel rod active region - 1.6% enr radial 0: Fuel 1.6%" region="-10034" universe="10008" />
-    <cell id="10054" material="10004" name="Fuel rod active region - 1.6% enr radial 1: Helium" region="10034 -10035" universe="10008" />
-    <cell id="10055" material="10006" name="Fuel rod active region - 1.6% enr radial 2: Zircaloy 4" region="10035 -10036" universe="10008" />
-    <cell id="10056" material="10014" name="Fuel rod active region - 1.6% enr radial outer: Borated Water" region="10036" universe="10008" />
-    <cell fill="10008" id="11273" name="root cell" region="10149 -10150 10151 -10152" universe="0" />
-    <surface coeffs="0.0 0.0 0.39218" id="10034" name="Fuel pellet OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.40005" id="10035" name="Fuel clad IR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.4572" id="10036" name="Fuel clad OR" type="z-cylinder" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10149" type="x-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10150" type="x-plane" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10151" type="y-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10152" type="y-plane" />
-</geometry>

pin-cell/fresh/materials.xml

@@ -1,267 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<materials>
-    <material id="10000" name="Air">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.00616" />
-        <nuclide ao="0.2094205995" name="O16" />
-        <nuclide ao="7.94005e-05" name="O17" />
-        <nuclide ao="0.7780395633" name="N14" />
-        <nuclide ao="0.0028604367000000003" name="N15" />
-        <nuclide ao="3.1124879999999996e-05" name="Ar36" />
-        <nuclide ao="5.86857e-06" name="Ar38" />
-        <nuclide ao="0.00929300655" name="Ar40" />
-        <nuclide ao="0.00027" name="C0" />
-    </material>
-    <material id="10001" name="SS304">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.03" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-    <material id="10002" name="Ag-In-Cd">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.16" />
-        <nuclide name="Ag107" wo="0.4110094082785408" />
-        <nuclide name="Ag109" wo="0.3889905917214592" />
-        <nuclide name="In113" wo="0.006314443289265887" />
-        <nuclide name="In115" wo="0.1436855567107341" />
-        <nuclide name="Cd106" wo="0.0005864650126662538" />
-        <nuclide name="Cd108" wo="0.0004261883300584398" />
-        <nuclide name="Cd110" wo="0.006095738560062021" />
-        <nuclide name="Cd111" wo="0.006311586256788057" />
-        <nuclide name="Cd112" wo="0.011999697873295025" />
-        <nuclide name="Cd113" wo="0.006140180186664414" />
-        <nuclide name="Cd114" wo="0.01456750341101345" />
-        <nuclide name="Cd116" wo="0.00387264036945234" />
-    </material>
-    <material id="10003" name="B4C">
-        <temperature>300</temperature>
-        <density units="g/cc" value="1.76" />
-        <nuclide name="B10" wo="0.14365010972394004" />
-        <nuclide name="B11" wo="0.6389498902760599" />
-        <nuclide name="C0" wo="0.2174" />
-    </material>
-    <material id="10004" name="Helium">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.0015981" />
-        <nuclide name="He3" wo="1.5070346049256974e-06" />
-        <nuclide name="He4" wo="0.999998492965395" />
-    </material>
-    <material id="10005" name="Inconel 718">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.2" />
-        <nuclide name="Si28" wo="0.003215573104901967" />
-        <nuclide name="Si29" wo="0.00016911126024954278" />
-        <nuclide name="Si30" wo="0.00011531563484849038" />
-        <nuclide name="Cr50" wo="0.007913309553017726" />
-        <nuclide name="Cr52" wo="0.15869399115925625" />
-        <nuclide name="Cr53" wo="0.018341120727338085" />
-        <nuclide name="Cr54" wo="0.004651578560387908" />
-        <nuclide name="Mn55" wo="0.0087" />
-        <nuclide name="Fe54" wo="0.016163233201258693" />
-        <nuclide name="Fe56" wo="0.26311407687664323" />
-        <nuclide name="Fe57" wo="0.006185135350045743" />
-        <nuclide name="Fe58" wo="0.0008375545720523535" />
-        <nuclide name="Ni58" wo="0.34398505352691505" />
-        <nuclide name="Ni60" wo="0.1370661540479713" />
-        <nuclide name="Ni61" wo="0.006057615154415727" />
-        <nuclide name="Ni62" wo="0.01963045531316453" />
-        <nuclide name="Ni64" wo="0.005160721957533462" />
-    </material>
-    <material id="10006" name="Zircaloy 4">
-        <temperature>300</temperature>
-        <density units="g/cc" value="6.55" />
-        <nuclide name="O16" wo="0.0012494965182849112" />
-        <nuclide name="O17" wo="5.034817150887735e-07" />
-        <nuclide name="Cr50" wo="4.1736864731106146e-05" />
-        <nuclide name="Cr52" wo="0.0008369936242576807" />
-        <nuclide name="Cr53" wo="9.673586881507429e-05" />
-        <nuclide name="Cr54" wo="2.4533642196138756e-05" />
-        <nuclide name="Fe54" wo="0.00011855672274761877" />
-        <nuclide name="Fe56" wo="0.001929932104229657" />
-        <nuclide name="Fe57" wo="4.536774095388075e-05" />
-        <nuclide name="Fe58" wo="6.143432068843669e-06" />
-        <nuclide name="Zr90" wo="0.49750307249921255" />
-        <nuclide name="Zr91" wo="0.10970127796055709" />
-        <nuclide name="Zr92" wo="0.16952409354767467" />
-        <nuclide name="Zr94" wo="0.17553856942304608" />
-        <nuclide name="Zr96" wo="0.02888298656950975" />
-        <nuclide name="Sn112" wo="0.0001325869644430062" />
-        <nuclide name="Sn114" wo="9.182449637587617e-05" />
-        <nuclide name="Sn115" wo="4.771905922545867e-05" />
-        <nuclide name="Sn116" wo="0.002058423153629443" />
-        <nuclide name="Sn117" wo="0.0010966473429083066" />
-        <nuclide name="Sn118" wo="0.0034879812938438245" />
-        <nuclide name="Sn119" wo="0.001247577110245757" />
-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10007" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
-        <nuclide name="P31" wo="0.00025" />
-        <nuclide name="S32" wo="0.00023692152702311576" />
-        <nuclide name="S33" wo="1.924704844422474e-06" />
-        <nuclide name="S34" wo="1.1112880999711348e-05" />
-        <nuclide name="S36" wo="4.088713275043879e-08" />
-        <nuclide name="Si28" wo="0.0036749406913165338" />
-        <nuclide name="Si29" wo="0.00019327001171376318" />
-        <nuclide name="Si30" wo="0.0001317892969697033" />
-        <nuclide name="Ni58" wo="0.005039827898909675" />
-        <nuclide name="Ni60" wo="0.002008197216956016" />
-        <nuclide name="Ni61" wo="8.875193135010345e-05" />
-        <nuclide name="Ni62" wo="0.00028761167190610265" />
-        <nuclide name="Ni64" wo="7.561128087810308e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006341263666702117" />
-        <nuclide name="Mo92" wo="0.0008769932056639445" />
-        <nuclide name="Mo94" wo="0.0005619573981472699" />
-        <nuclide name="Mo95" wo="0.0009812790231824658" />
-        <nuclide name="Mo96" wo="0.0010415835207694215" />
-        <nuclide name="Mo97" wo="0.0006048497176301975" />
-        <nuclide name="Mo98" wo="0.00154921076793649" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.506648724403529e-06" />
-        <nuclide name="B11" wo="2.449335127559647e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10008" name="Fuel 1.6%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.9992419999999993" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10009" name="Fuel 2.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.9992420000000004" name="O16" />
-        <nuclide ao="0.0007580000000000002" name="O17" />
-        <nuclide ao="0.00019522327124383906" name="U234" />
-        <nuclide ao="0.024298776982208985" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10010" name="Fuel 3.1%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.9992420000000022" name="O16" />
-        <nuclide ao="0.0007580000000000009" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-    <material id="10011" name="Fuel 3.2%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.34115" />
-        <nuclide ao="1.9992419999999995" name="O16" />
-        <nuclide ao="0.0007579999999999998" name="O17" />
-        <nuclide ao="0.00025991006602092703" name="U234" />
-        <nuclide ao="0.03235012244921097" name="U235" />
-        <nuclide ao="0.9673899674847681" name="U238" />
-    </material>
-    <material id="10012" name="Fuel 3.4%">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.35917" />
-        <nuclide ao="1.999241999999999" name="O16" />
-        <nuclide ao="0.0007579999999999997" name="O17" />
-        <nuclide ao="0.0002770142199967032" name="U234" />
-        <nuclide ao="0.03447901835531245" name="U235" />
-        <nuclide ao="0.9652439674246908" name="U238" />
-    </material>
-    <material id="10013" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.013479369482225239" name="B10" />
-        <nuclide ao="0.054735873774104264" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10014" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10015" name="Water SPN">
-        <density units="g/cc" value="0.9810025319057221" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10016" name="SS SPN">
-        <temperature>300</temperature>
-        <density units="g/cc" value="3.6838480704877297" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-</materials>

pin-cell/fresh/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="fuel-pin" id="10020" type="slice">
-        <origin>0.0 0.0 inf</origin>
-        <width>1.25984 1.25984</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

pin-cell/fresh/settings.xml

@@ -1,18 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>10</batches>
-        <inactive>5</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-0.62992 -0.62992 -10.0 0.62992 0.62992 10.0</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

pin-cell/fresh/tallies.xml

@@ -1,111 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="10042">
-        <filter bins="10004 10006 10008 10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10013">
-        <filter bins="10004 10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10046">
-        <filter bins="10004 10006 10008 10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10020">
-        <filter bins="10004 10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10023">
-        <filter bins="10004 10006" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10024">
-        <filter bins="10004 10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10015">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10031">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10033">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10035">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10036">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10043">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10045">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10047">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10048">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

pin-cell/geometry.py

@@ -1,79 +0,0 @@
-"""Creates a 2D fuel pin cell with reflective BCs."""
-
-import numpy as np
-
-import openmc
-from beavrs.builder import BEAVRS
-
-
-def find_pin(pin_name, wrap_geometry=True):
-    """Find a fuel pin with some string name in the BEAVRS OpenMC model.
-
-    This method extracts the pin cell and wraps it in an OpenMC Geometry.
-    The returned geometry has reflective boundary conditions along the x and y
-    boundaries. The z-axis left unbounded.
-
-    Parameters
-    ----------
-    pin_name : str
-        The name of the fuel pin universe
-    wrap_geometry : bool
-        If false, the pin cell Universe is returned. If true, the pin cell
-        Universe is wrapped in an OpenMC Geometry and returned (default).
-
-    Returns
-    -------
-    openmc.Universe
-        The OpenMC Universe or Geometry for this fuel pin or None if not found
-
-    """
-
-    # Get all OpenMC Universes
-    all_univ = beavrs.main_universe.get_all_universes()
-
-    # Iterate over all Universes
-    fuel_pin = None
-    for univ_id, univ in all_univ.items():
-        if univ._name == pin_name:
-            fuel_pin = univ
-
-    # Wrap pin cell Universe in a Geometry if requested by the user
-    if wrap_geometry:
-
-        # Make reflective boundaries
-        pin_pitch = 0.62992
-        min_x = openmc.XPlane(x0=-pin_pitch, boundary_type='reflective')
-        max_x = openmc.XPlane(x0=pin_pitch, boundary_type='reflective')
-        min_y = openmc.YPlane(y0=-pin_pitch, boundary_type='reflective')
-        max_y = openmc.YPlane(y0=pin_pitch, boundary_type='reflective')
-
-        # Create a root Cell
-        root_cell = openmc.Cell(name='root cell')
-        root_cell.fill = fuel_pin
-
-        # Add boundaries to the root Cell
-        root_cell.add_surface(surface=min_x, halfspace=+1)
-        root_cell.add_surface(surface=max_x, halfspace=-1)
-        root_cell.add_surface(surface=min_y, halfspace=+1)
-        root_cell.add_surface(surface=max_y, halfspace=-1)
-
-        # Create a root Universe
-        root_univ = openmc.Universe(universe_id=0, name='root universe')
-        root_univ.add_cell(root_cell)
-
-        # Create a Geometry
-        fuel_pin = openmc.Geometry()
-        fuel_pin.root_universe = root_univ
-
-    return fuel_pin
-
-
-# User-specified enrichment of 1.6, 2.4 or 3.1 percent
-enrichment = 1.6
-
-# Instantiate a BEAVRS object
-beavrs = BEAVRS()
-
-# Extract fuel pin of interest from BEAVRS model
-pin_name = 'Fuel rod active region - {}% enr'.format(enrichment)
-openmc_geometry = find_pin(pin_name)

pin-cell/geometry.xml

@@ -1,15 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10077" material="10008" name="Fuel rod active region - 1.6% enr radial 0: fuel 1.6%" region="(-10055)" universe="45" />
-    <cell id="10290" material="10014" name="Fuel rod active region - 1.6% enr radial outer: water" region="(10004)" universe="45" />
-    <cell id="10468" material="10006" name="Fuel rod active region - 1.6% enr radial 2: zirc" region="(10056 -10004)" universe="45" />
-    <cell id="10532" material="10004" name="Fuel rod active region - 1.6% enr radial 1: helium" region="(10055 -10056)" universe="45" />
-    <cell fill="45" id="10533" name="root cell" region="(10057 -10058 10059 -10060)" universe="0" />
-    <surface coeffs="0.0 0.0 0.4572" id="10004" name="Fuel clad OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.39218" id="10055" name="Fuel pellet OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 0.40005" id="10056" name="Fuel clad IR" type="z-cylinder" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10057" type="x-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10058" type="x-plane" />
-    <surface boundary="reflective" coeffs="-0.62992" id="10059" type="y-plane" />
-    <surface boundary="reflective" coeffs="0.62992" id="10060" type="y-plane" />
-</geometry>

pin-cell/materials.xml

@@ -1,250 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<materials>
-    <material id="10000" name="air">
-        <density units="g/cc" value="0.000616" />
-        <nuclide ao="5.297187137931348e-06" name="O16" />
-        <nuclide ao="2.013696317014378e-09" name="O17" />
-        <nuclide ao="1.9680587495341365e-05" name="N14" />
-        <nuclide ao="7.189905102878735e-08" name="N15" />
-        <nuclide ao="7.872887353789031e-10" name="Ar36" />
-        <nuclide ao="1.4844263026178957e-10" name="Ar38" />
-        <nuclide ao="2.350620909901456e-07" name="Ar40" />
-        <nuclide ao="6.8295189749262915e-09" name="C0" />
-    </material>
-    <material id="10001" name="SS304">
-        <density units="g/cc" value="8.03" />
-        <nuclide ao="0.0009527579226852701" name="Si28" />
-        <nuclide ao="4.840084217364964e-05" name="Si29" />
-        <nuclide ao="3.194352273232117e-05" name="Si30" />
-        <nuclide ao="0.0007677840970776607" name="Cr50" />
-        <nuclide ao="0.014805952062149621" name="Cr52" />
-        <nuclide ao="0.0016788761119297705" name="Cr53" />
-        <nuclide ao="0.0004179077996751824" name="Cr54" />
-        <nuclide ao="0.0017604484151274116" name="Mn55" />
-        <nuclide ao="0.003461966196285883" name="Fe54" />
-        <nuclide ao="0.054345465590079536" name="Fe56" />
-        <nuclide ao="0.001255073801527765" name="Fe57" />
-        <nuclide ao="0.00016702728269505883" name="Fe58" />
-        <nuclide ao="0.005608899288456394" name="Ni58" />
-        <nuclide ao="0.002160526551422537" name="Ni60" />
-        <nuclide ao="9.391695137728518e-05" name="Ni61" />
-        <nuclide ao="0.00029945657643291586" name="Ni62" />
-        <nuclide ao="7.625242433518505e-05" name="Ni64" />
-    </material>
-    <material id="10002" name="aic_rod">
-        <density units="g/cc" value="10.16" />
-        <nuclide ao="0.023523277622876513" name="Ag107" />
-        <nuclide ao="0.0218542906613815" name="Ag109" />
-        <nuclide ao="0.0003429124374343743" name="In113" />
-        <nuclide ao="0.007650384472457801" name="In115" />
-        <nuclide ao="3.401764773515755e-05" name="Cd106" />
-        <nuclide ao="2.4220565187432173e-05" name="Cd108" />
-        <nuclide ao="0.00033990433616969416" name="Cd110" />
-        <nuclide ao="0.0003483407128080133" name="Cd111" />
-        <nuclide ao="0.0006566766718794812" name="Cd112" />
-        <nuclide ao="0.00033255652425890015" name="Cd113" />
-        <nuclide ao="0.000781861615544861" name="Cd114" />
-        <nuclide ao="0.000203833745229064" name="Cd116" />
-    </material>
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-        <nuclide ao="0.00030805872184899507" name="O16" />
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-        <nuclide ao="2.2307656270713298e-05" name="Sn122" />
-        <nuclide ao="2.7896615509164147e-05" name="Sn124" />
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-        <nuclide ao="3.0046375086894216e-05" name="Mo100" />
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-        <nuclide ao="1.1374571820163181e-07" name="Ca42" />
-        <nuclide ao="2.3733650629397675e-08" name="Ca43" />
-        <nuclide ao="3.667288534290633e-07" name="Ca44" />
-        <nuclide ao="7.032192779080792e-10" name="Ca46" />
-        <nuclide ao="3.28755012422027e-08" name="Ca48" />
-        <nuclide ao="2.5933050454431966e-06" name="B10" />
-        <nuclide ao="1.0438378600000003e-05" name="B11" />
-        <nuclide ao="1.2143798614651014e-06" name="Ti46" />
-        <nuclide ao="1.0951498387030732e-06" name="Ti47" />
-        <nuclide ao="1.0851404046934214e-05" name="Ti48" />
-        <nuclide ao="7.963387940031755e-07" name="Ti49" />
-        <nuclide ao="7.624833554411181e-07" name="Ti50" />
-        <nuclide ao="4.352300342324809e-05" name="Al27" />
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-        <nuclide ao="0.07446549365217064" name="Fe56" />
-        <nuclide ao="0.0017197329931005689" name="Fe57" />
-        <nuclide ao="0.0002288648910119681" name="Fe58" />
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-    <material id="10008" name="fuel 1.6%">
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="0.04598903962223639" name="O16" />
-        <nuclide ao="1.748247839824116e-05" name="O17" />
-        <nuclide ao="3.0130672291707784e-06" name="U234" />
-        <nuclide ao="0.0003750262359227545" name="U235" />
-        <nuclide ao="0.022625221747165396" name="U238" />
-    </material>
-    <material id="10009" name="fuel 2.4%">
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="0.04592213822608188" name="O16" />
-        <nuclide ao="1.7457046203468432e-05" name="O17" />
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-        <nuclide ao="0.0005581379894229944" name="U235" />
-        <nuclide ao="0.02240717540768732" name="U238" />
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-    <material id="10010" name="fuel 3.1%">
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="0.04594445511692833" name="O16" />
-        <nuclide ao="1.746552984577416e-05" name="O17" />
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-    <material id="10011" name="fuel 3.2%">
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-        <nuclide ao="0.046121066900227325" name="O16" />
-        <nuclide ao="1.7532667835864017e-05" name="O17" />
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-    <material id="10012" name="fuel 3.4%">
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-        <nuclide ao="0.0462025426228367" name="O16" />
-        <nuclide ao="1.7563640380022353e-05" name="O17" />
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-        <nuclide ao="3.221031668792071e-05" name="B11" />
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pin-cell/plots.xml

@@ -1,23 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <plot basis="xy" color="mat" filename="fuel-pin" id="10020" type="slice">
-        <origin>0.0 0.0 inf</origin>
-        <width>1.25984 1.25984</width>
-        <pixels>1000 1000</pixels>
-        <col_spec id="10016" rgb="112 128 144" />
-        <col_spec id="10000" rgb="255 255 255" />
-        <col_spec id="10001" rgb="0 0 0" />
-        <col_spec id="10002" rgb="255 0 0" />
-        <col_spec id="10003" rgb="200 50 50" />
-        <col_spec id="10004" rgb="255 218 185" />
-        <col_spec id="10005" rgb="101 101 101" />
-        <col_spec id="10006" rgb="111 111 111" />
-        <col_spec id="10007" rgb="50 50 50" />
-        <col_spec id="10008" rgb="142 35 35" />
-        <col_spec id="10009" rgb="255 215 0" />
-        <col_spec id="10010" rgb="0 0 128" />
-        <col_spec id="10013" rgb="0 255 0" />
-        <col_spec id="10014" rgb="198 226 255" />
-        <col_spec id="10015" rgb="176 196 222" />
-    </plot>
-</plots>

pin-cell/settings.xml

@@ -1,22 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>10</batches>
-        <inactive>5</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-0.62992 -0.62992 -10.0 0.62992 0.62992 10.0</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <source_point>
-        <write>false</write>
-    </source_point>
-    <ptables>true</ptables>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

pin-cell/tallies.xml

@@ -1,111 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <tally id="10042">
-        <filter bins="10004 10006 10008 10014" type="material" />
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-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
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-    <tally id="10013">
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-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10046">
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-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
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-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
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-    <tally id="10023">
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-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10024">
-        <filter bins="10004 10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>He3 He4 O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
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-    <tally id="10015">
-        <filter bins="10006" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10031">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10033">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10035">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10036">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10043">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10045">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energy" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10047">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 20000000.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10048">
-        <filter bins="10014" type="material" />
-        <filter bins="0.0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.042 0.05 0.058 0.067 0.08 0.1 0.14 0.18 0.22 0.25 0.28 0.3 0.32 0.35 0.4 0.5 0.625 0.78 0.85 0.91 0.95 0.972 0.996 1.02 1.045 1.071 1.097 1.123 1.15 1.3 1.5 1.855 2.1 2.6 3.3 4.0 9.877 15.968 27.7 48.052 75.501 148.73 367.26001 906.90002 1425.1 2239.5 3519.1 5530.0 9118.0 15030.0 24780.0 40850.0 67340.0 111000.0 183000.0 302500.0 500000.0 821000.0 1353000.0 2231000.0 3679000.0 6065500.0 20000000.0" type="energyout" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

profile.py

@@ -1,85 +0,0 @@
-"""A parametric study over MPI procs and OMP threads for a benchmark."""
-
-import os
-import glob
-import numpy as np
-import openmc
-
-# Query user for benchmark to profile (i.e., '2x2-periodic')
-benchmark = input('Benchmark: ')
-os.chdir(benchmark)
-
-# Query user for hardware platform to consider
-platform = os.environ['HOSTNAME']
-
-# Default MPI+OMP runtime parameters for Phi/Haswell
-if 'thing' in platform:
-    platform = 'haswell'
-    mpi_procs = [1, 2, 4, 8, 36, 72]
-    omp_threads = [72, 36, 18, 9, 2, 1]
-else:
-    platform = 'phi'
-    mpi_procs = [4, 4, 4, 64, 64, 64]
-    omp_threads = [16, 32, 64, 1, 2, 4]
-
-# Allocate arrays for timing data for inactive and active cycles
-times = np.zeros((len(mpi_procs),2), dtype=np.int)
-
-# Instantiate a Summary object to retrieve the geometry
-su = openmc.Summary('summary.h5')
-
-for i, xs in enumerate(['ace', 'multipole']):
-
-    # Construct uniform initial source distribution over fissionable zones
-    lower_left = su.opencg_geometry.bounds[:2] + [-10.]
-    upper_right = su.opencg_geometry.bounds[3:5] + [10.]
-    source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-    source.space.only_fissionable = True
-
-    settings_file = openmc.Settings()
-    settings_file.batches = 10
-    settings_file.inactive = 5
-    settings_file.particles = 10000
-    settings_file.ptables = True
-    settings_file.output = {'tallies': False}
-    settings_file.source = source
-    settings_file.sourcepoint_write = False
-
-    if xs == 'multipole':
-        settings_file.temperature = {'multipole': True, 'tolerance': 1000}
-
-    settings_file.export_to_xml()
-
-    for j, (procs, threads) in enumerate(zip(mpi_procs, omp_threads)):
-
-        # Run OpenMC - works for both flat and cache memory modes
-        #openmc.run(threads=threads, mpi_procs=procs,
-        #           mpi_exec='HYDRA_TOPO_DEBUG=1 mpiexec -bind-to numa')
-
-        # Run OpenMC - works for both flat mode with MCDRAM only
-        #openmc.run(threads=threads, mpi_procs=procs,
-        #           mpi_exec='HYDRA_TOPO_DEBUG=1 mpiexec -bind-to core:16 numactl --preferred 4,5,6,7')
-
-        # Run OpenMC - works for both flat and cache memory modes
-        openmc.run(threads=threads, mpi_procs=procs,
-                   mpi_exec='HYDRA_TOPO_DEBUG=1 mpiexec -bind-to core:16')
-
-        # Glob the names of all statepoints in the directory
-        sp_filenames = glob.glob('statepoint.*.h5')
-
-        # Load the final statepoint
-        sp = openmc.StatePoint(sp_filenames[0])
-
-        # Extract cumulative time spent in (in)active cycles in seconds
-        inactive = sp.runtime['inactive batches']
-        active = sp.runtime['active batches']
-
-        # Convert times to neutrons / second
-        times[j,0] = int((sp.n_inactive * sp.n_particles) / inactive)
-        times[j,1] = int((sp.n_realizations * sp.n_particles) / active)
-
-        print('inactive time (n / sec): {}'.format(times[j,0]))
-        print('active time (n / sec): {}'.format(times[j,1]))
-
-    # Save timing data to CSV files
-    np.savetxt('{}-{}.csv'.format(platform, xs), times, delimiter=',', fmt='%d')

smr/build-assembly-long.py

@@ -0,0 +1,186 @@
+#!/usr/bin/env python3
+
+import argparse
+from math import pi, isclose
+from pathlib import Path
+
+import numpy as np
+from tqdm import tqdm
+import openmc
+
+from smr.materials import materials, clone
+from smr.surfaces import surfs, lattice_pitch, pin_pitch, bottom_fuel_stack, \
+    top_active_core, pellet_OR, active_fuel_length
+from smr.pins import pin_universes, make_stack
+
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', dest='multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('--clone', action='store_true',
+                    help='Clone materials for each cell instance')
+parser.add_argument('--no-clone', dest='clone', action='store_false',
+                    help='Do not clone materials for each cell instance')
+parser.add_argument('-a', '--axial', type=int, default=100,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(clone=False, multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('assembly-long-depleted')
+    else:
+        directory = Path('assembly-long-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+rings = [0.1*pin_pitch, 0.2*pin_pitch]
+
+assembly_long_surfs = [
+    surfs['bottom FR'],
+    surfs['bot active core'],
+    surfs['top active core'],
+    surfs['top pin plenum'],
+    surfs['top FR'],
+    surfs['bot upper nozzle'],
+    surfs['top upper nozzle']
+]
+
+univs = pin_universes(rings, args.axial, args.depleted)
+fuel_univ = make_stack(
+    'Fuel (3.1%) stack no grid',
+    surfaces=assembly_long_surfs,
+    universes=[
+        univs['water pin'],
+        univs['end plug'],
+        univs['Fuel pin (3.1%) no grid'],
+        univs['pin plenum'],
+        univs['end plug'],
+        univs['water pin']
+    ]
+)
+
+# Define the NumPy array indices for assembly locations where there
+# may be CR guide tubes, instrument tubes and burnable absorbers
+nonfuel_y = np.array([2,2,2,3,3,5,5,5,5,5,8,8,8,8,8,11,11,11,11,11,13,13,14,14,14])
+nonfuel_x = np.array([5,8,11,3,13,2,5,8,11,14,2,5,8,11,14,2,5,8,11,14,3,13,5,8,11])
+
+universes = np.full((17,17), fuel_univ)
+universes[nonfuel_y, nonfuel_x] = univs['GT empty']
+
+# Instantiate the lattice
+lattice = openmc.RectLattice(name='Pin lattice')
+lattice.lower_left = (-17.*pin_pitch/2., -17.*pin_pitch/2.)
+lattice.pitch = (pin_pitch, pin_pitch)
+lattice.universes = universes
+
+# Add lattice to bounding cell
+root_universe = openmc.Universe(name='Root universe')
+cell = openmc.Cell(name='Lattice cell')
+cell.fill = lattice
+z_bounds = +surfs['bottom FR'] & -surfs['top FR']
+cell.region = surfs['lat grid box inner'] & z_bounds
+root_universe.add_cell(cell)
+
+# Apply reflective boundaries on sides and vacuum on bottom/top
+surfs['bottom FR'].boundary_type = 'vacuum'
+surfs['top FR'].boundary_type = 'vacuum'
+for halfspace in surfs['lat grid box inner']:
+    halfspace.surface.boundary_type = 'reflective'
+
+# Define geometry with a single assembly
+geometry = openmc.Geometry(root_universe)
+
+h = active_fuel_length / args.axial
+
+fuel_mats = {}
+
+# Count the number of instances for each cell and material
+if args.clone:
+    geometry.determine_paths(instances_only=True)
+
+for cell in tqdm(geometry.get_all_material_cells().values(),
+                 desc='Differentiating materials / assigning volume'):
+    if cell.fill in materials:
+        # Determine if this material is fuel
+        is_fuel = 'UO2 Fuel' in cell.fill.name
+
+        # Fill cell with list of "differentiated" materials if requested
+        if args.clone:
+            cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
+
+        # Determine volume of each fuel material
+        if is_fuel:
+            upper_right = cell.region.bounding_box[1]
+            if isclose(upper_right[0], rings[0]):
+                ri, ro = 0.0, rings[0]
+            elif isclose(upper_right[0], rings[1]):
+                ri, ro = rings[0], rings[1]
+            else:
+                ri, ro = rings[1], pellet_OR
+
+            if args.clone:
+                for mat in cell.fill:
+                    mat.volume = pi * (ro*ro - ri*ri) * h
+            else:
+                # In non-clone mode, we still need to create a copy of the
+                # material for each ring since they get different volumes
+                if ri not in fuel_mats:
+                    cell.fill = cell.fill.clone()
+                    cell.fill.volume = pi * (ro*ro - ri*ri) * h
+                    fuel_mats[ri] = cell.fill
+                else:
+                    cell.fill = fuel_mats[ri]
+        else:
+            if args.clone:
+                for mat in cell.fill:
+                    mat.volume = 1.0
+            else:
+                cell.fill.volume = 1.0
+
+#### Create OpenMC "materials.xml" file
+print('Getting materials...')
+all_materials = geometry.get_all_materials()
+print('Creating materials collection...')
+materials = openmc.Materials(all_materials.values())
+print('Exporting materials to XML...')
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = (-lattice_pitch/2, -lattice_pitch/2, bottom_fuel_stack)
+upper_right = (lattice_pitch/2, lattice_pitch/2, top_active_core)
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 10000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+settings.temperature = {
+    'default': 531.5,
+    'method': 'interpolation',
+        'range': (500.0, 1300.0)
+}
+if args.multipole:
+    settings.temperature['multipole'] = True
+    settings.temperature['tolerance'] = 1000
+
+settings.export_to_xml(str(directory / 'settings.xml'))

smr/build-assembly-short.py

@@ -0,0 +1,192 @@
+#!/usr/bin/env python3
+
+import argparse
+from math import pi, isclose
+from pathlib import Path
+
+import numpy as np
+from tqdm import tqdm
+import openmc
+
+from smr.materials import materials, clone
+from smr.surfaces import surfs, lattice_pitch, pin_pitch, bottom_fuel_stack, \
+    top_active_core, pellet_OR, clad_OR, clad_IR, guide_tube_IR, guide_tube_OR
+from smr.pins import pin_universes
+
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('-t', '--tallies', choices=('cell', 'mat'), default='mat',
+                    help='Whether to use distribmats or distribcells for tallies')
+parser.add_argument('-a', '--axial', type=int, default=10,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('assembly-short-depleted')
+    else:
+        directory = Path('assembly-short-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+rings = [0.1*pin_pitch, 0.2*pin_pitch]
+
+# Define the NumPy array indices for assembly locations where there
+# may be CR guide tubes, instrument tubes and burnable absorbers
+nonfuel_y = np.array([2,2,2,3,3,5,5,5,5,5,8,8,8,8,8,11,11,11,11,11,13,13,14,14,14])
+nonfuel_x = np.array([5,8,11,3,13,2,5,8,11,14,2,5,8,11,14,2,5,8,11,14,3,13,5,8,11])
+
+# NO BURNABLE ABSORBERS
+pins = pin_universes(rings, args.axial, args.depleted)
+gtu = pins['GT empty']
+#gti = pins['GT empty instr']
+universes = np.empty((17,17), dtype=openmc.Universe)
+universes[:,:] = pins['Fuel pin (3.1%) no grid']
+universes[nonfuel_y, nonfuel_x] = [    gtu,   gtu,   gtu,
+                                     gtu,              gtu,
+                                   gtu, gtu,  gtu,  gtu, gtu,
+                                   gtu, gtu,  gtu,  gtu, gtu,
+                                   gtu, gtu,  gtu,  gtu, gtu,
+                                     gtu,              gtu,
+                                       gtu,   gtu,   gtu     ]
+
+# Instantiate the lattice
+lattice = openmc.RectLattice(name='Pin lattice')
+lattice.lower_left = (-17.*pin_pitch/2., -17.*pin_pitch/2.)
+lattice.pitch = (pin_pitch, pin_pitch)
+lattice.universes = universes
+
+# Add lattice to bounding cell
+root_universe = openmc.Universe(name='Root universe')
+cell = openmc.Cell(name='Lattice cell')
+cell.fill = lattice
+z_bounds = +surfs['bot active core'] & -surfs['top active core']
+cell.region = surfs['lat grid box inner'] & z_bounds
+root_universe.add_cell(cell)
+
+# Apply reflective boundaries
+surfs['bot active core'].boundary_type = 'reflective'
+surfs['top active core'].boundary_type = 'reflective'
+for halfspace in surfs['lat grid box inner']:
+    halfspace.surface.boundary_type = 'reflective'
+
+# Define geometry with a single assembly
+geometry = openmc.Geometry(root_universe)
+
+#### "Differentiate" the geometry if using distribmats
+h = 10.0*pin_pitch / args.axial
+if args.tallies == 'mat':
+    # Count the number of instances for each cell and material
+    geometry.determine_paths(instances_only=True)
+
+    for cell in tqdm(geometry.get_all_material_cells().values(),
+                     desc='Differentiating materials'):
+        if cell.fill in materials:
+            # Fill cell with list of "differentiated" materials
+            cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
+
+            # Determine volume of each fuel material
+            if 'UO2 Fuel' in cell.fill[0].name:
+                lower_left, _ = cell.region.bounding_box
+                if isclose(lower_left[0], rings[0]):
+                    ri, ro = 0.0, rings[0]
+                elif isclose(lower_left[0], rings[1]):
+                    ri, ro = rings[0], rings[1]
+                else:
+                    ri, ro = rings[1], pellet_OR
+                for mat in cell.fill:
+                    mat.volume = pi * (ro*ro - ri*ri) * h
+            elif cell.fill[0].name == 'Borated Water':
+                for mat in cell.fill:
+                    mat.volume = pin_pitch**2 - pi*clad_OR**2 * h
+            elif cell.fill[0].name == 'Helium':
+                for mat in cell.fill:
+                    mat.volume = pi * (clad_IR**2 - pellet_OR**2) * h
+            elif cell.fill[0].name == 'M5':
+                for mat in cell.fill:
+                    mat.volume = pi * (clad_OR**2 - clad_IR**2) * h
+            elif cell.fill[0].name == 'Zircaloy-4':
+                for mat in cell.fill:
+                    mat.volume = pi * (guide_tube_OR**2 - guide_tube_IR**2) * h
+
+#### Create OpenMC "materials.xml" file
+print('Getting materials...')
+all_materials = geometry.get_all_materials()
+print('Creating materials collection...')
+materials = openmc.Materials(all_materials.values())
+print('Exporting materials to XML...')
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = (-lattice_pitch/2, -lattice_pitch/2, bottom_fuel_stack)
+upper_right = (lattice_pitch/2, lattice_pitch/2, top_active_core)
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 10000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+
+if args.multipole:
+    settings.temperature = {
+        'multipole': True,
+        'tolerance': 1000,
+        'default': 531.5,
+        'method': 'interpolation',
+        'range': (500.0, 1300.0)
+    }
+
+settings.export_to_xml(str(directory / 'settings.xml'))
+
+
+####  Create OpenMC "tallies.xml" file
+tallies = openmc.Tallies()
+
+# Extract all fuel materials
+materials = geometry.get_materials_by_name(name='Fuel', matching=False)
+
+# If using distribcells, create distribcell tally needed for depletion
+if args.tallies == 'cell':
+    # Extract all cells filled by a fuel material
+    fuel_cells = []
+    for cell in geometry.get_all_cells().values():
+        if cell.fill in materials:
+            tally = openmc.Tally(name='depletion tally')
+            tally.scores = ['(n,p)', '(n,a)', '(n,gamma)',
+                            'fission', '(n,2n)', '(n,3n)', '(n,4n)']
+            tally.nuclides = cell.fill.get_nuclides()
+            tally.filters.append(openmc.DistribcellFilter([cell]))
+            tallies.append(tally)
+
+# If using distribmats, create material tally needed for depletion
+elif args.tallies == 'mat':
+    tally = openmc.Tally(name='depletion tally')
+    tally.scores = ['(n,p)', '(n,a)', '(n,gamma)',
+                    'fission', '(n,2n)', '(n,3n)', '(n,4n)']
+    tally.nuclides = materials[0].get_nuclides()
+    tally.filters = [openmc.MaterialFilter(materials)]
+    tallies.append(tally)
+
+tallies.export_to_xml(str(directory / 'tallies.xml'))

smr/build-assembly.py

@@ -0,0 +1,145 @@
+#!/usr/bin/env python3
+
+import argparse
+from pathlib import Path
+
+import numpy as np
+from tqdm import tqdm
+
+import openmc
+from smr.materials import materials, clone
+from smr.surfaces import surfs, lattice_pitch, bottom_fuel_stack, top_active_core, pellet_OR
+from smr.assemblies import assembly_universes
+from smr import inlet_temperature
+
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', dest='multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('--clone', action='store_true',
+                    help='Clone materials for each cell instance')
+parser.add_argument('--no-clone', dest='clone', action='store_false',
+                    help='Do not clone materials for each cell instance')
+parser.add_argument('-t', '--tallies', choices=('cell', 'mat'), default='mat',
+                    help='Whether to use distribmats or distribcells for tallies')
+parser.add_argument('-r', '--rings', type=int, default=10,
+                    help='Number of annular regions in fuel')
+parser.add_argument('-a', '--axial', type=int, default=196,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(clone=False, multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('assembly-depleted')
+    else:
+        directory = Path('assembly-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+# Define geometry with a single assembly
+if args.rings > 1:
+    ring_radii = np.sqrt(np.arange(1, args.rings)*pellet_OR**2 / args.rings)
+else:
+    ring_radii = None
+assembly = assembly_universes(ring_radii, args.axial, args.depleted)
+lattice_sides = openmc.model.rectangular_prism(lattice_pitch, lattice_pitch,
+                                               boundary_type='reflective')
+main_cell = openmc.Cell(
+    fill=assembly['Assembly (3.1%)'],
+    region=lattice_sides & +surfs['lower bound'] & -surfs['upper bound']
+)
+root_univ = openmc.Universe(cells=[main_cell])
+geometry = openmc.Geometry(root_univ)
+
+#### "Differentiate" the geometry if using distribmats
+if args.clone:
+    # Count the number of instances for each cell and material
+    geometry.determine_paths(instances_only=True)
+
+    # Extract all cells filled by a fuel material
+    fuel_mats = {m for m in materials if 'UO2 Fuel' in m.name}
+
+    for cell in tqdm(geometry.get_all_material_cells().values(),
+                     desc='Differentiating materials'):
+        if cell.fill in fuel_mats:
+            # Fill cell with list of "differentiated" materials
+            cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
+
+#### Create OpenMC "materials.xml" file
+print('Getting materials...')
+all_materials = geometry.get_all_materials()
+print('Creating materials collection...')
+materials = openmc.Materials(all_materials.values())
+print('Exporting materials to XML...')
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = (-lattice_pitch/2, -lattice_pitch/2, bottom_fuel_stack)
+upper_right = (lattice_pitch/2, lattice_pitch/2, top_active_core)
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 10000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+settings.temperature = {
+    'default': inlet_temperature,
+    'method': 'interpolation',
+    'range': (300.0, 1500.0),
+}
+if args.multipole:
+    settings.temperature['multipole'] = True
+    settings.temperature['tolerance'] = 1000
+
+settings.export_to_xml(str(directory / 'settings.xml'))
+
+
+####  Create OpenMC "tallies.xml" file
+tallies = openmc.Tallies()
+
+# Extract all fuel materials
+materials = geometry.get_materials_by_name(name='Fuel', matching=False)
+
+# If using distribcells, create distribcell tally needed for depletion
+if args.tallies == 'cell':
+    # Extract all cells filled by a fuel material
+    fuel_cells = []
+    for cell in geometry.get_all_cells().values():
+        if cell.fill in materials:
+            tally = openmc.Tally(name='depletion tally')
+            tally.scores = ['(n,p)', '(n,a)', '(n,gamma)',
+                            'fission', '(n,2n)', '(n,3n)', '(n,4n)']
+            tally.nuclides = cell.fill.get_nuclides()
+            tally.filters.append(openmc.DistribcellFilter([cell]))
+            tallies.append(tally)
+
+# If using distribmats, create material tally needed for depletion
+elif args.tallies == 'mat':
+    tally = openmc.Tally(name='depletion tally')
+    tally.scores = ['(n,p)', '(n,a)', '(n,gamma)',
+                    'fission', '(n,2n)', '(n,3n)', '(n,4n)']
+    tally.nuclides = materials[0].get_nuclides()
+    tally.filters = [openmc.MaterialFilter(materials)]
+    tallies.append(tally)
+
+tallies.export_to_xml(str(directory / 'tallies.xml'))

smr/build-core-depleted.py

@@ -0,0 +1,72 @@
+#!/usr/bin/env python3
+
+import numpy as np
+import opendeplete
+
+from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
+from smr.core import geometry
+
+
+# FIXME: Automatically extract info needed to calculate burnable cell volumes
+# Fuel rod geometric parameters
+radius = 0.39218
+height = 200.
+
+# Count the number of instances for each cell and material
+geometry.determine_paths(instances_only=True)
+
+# Extract all cells filled by a fuel material
+fuel_cells = geometry.get_cells_by_name(
+    name='(1.6%) (0)', case_sensitive=True)
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(1.6%) grid (bottom) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(1.6%) grid (intermediate) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(2.4%) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(2.4%) grid (bottom) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(2.4%) grid (intermediate) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(3.1%) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(3.1%) grid (bottom) (0)', case_sensitive=True))
+fuel_cells.extend(geometry.get_cells_by_name(
+    name='(3.1%) grid (intermediate) (0)', case_sensitive=True))
+
+# Assign distribmats for each material
+for cell in fuel_cells:
+    cell.fill.volume = np.pi * radius**2 * height
+    cell.fill.depletable = True
+    cell.fill.temperature = 300.0
+
+    cell.fill = [cell.fill.clone() for i in range(cell.num_instances)]
+
+# Create dt vector for 1 month with 5 day timesteps
+dt1 = 5*24*60*60  # 5 days
+dt2 = 1.*30*24*60*60  # 1 months
+N = np.floor(dt2/dt1)
+dt = np.repeat([dt1], N)
+
+# Create settings variable
+settings = opendeplete.OpenMCSettings()
+settings.openmc_call = "openmc"
+settings.particles = 1000000
+settings.batches = 200
+settings.inactive = 100
+settings.lower_left = \
+    [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
+settings.upper_right = \
+    [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
+settings.entropy_dimension = [15, 15, 1]
+
+# MeV/second cm from CASMO
+settings.power = 2.337e15 * ((17.*17.*37.) / 1.5**2) * height
+settings.dt_vec = dt
+settings.output_dir = 'core-depleted'
+
+op = opendeplete.OpenMCOperator(geometry, settings)
+
+# Perform simulation using the MCNPX/MCNP6 algorithm
+opendeplete.cecm(op)

smr/build-core-fresh.py

@@ -0,0 +1,121 @@
+#!/usr/bin/env python3
+
+import argparse
+from math import pi
+from pathlib import Path
+
+import numpy as np
+import openmc
+from tqdm import tqdm
+
+from smr.materials import materials, clone
+from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core, \
+    pellet_OR, active_fuel_length
+from smr.core import core_geometry
+from smr import inlet_temperature
+
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', dest='multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('--clone', action='store_true',
+                    help='Clone materials for each cell instance')
+parser.add_argument('--no-clone', dest='clone', action='store_false',
+                    help='Do not clone materials for each cell instance')
+parser.add_argument('-r', '--rings', type=int, default=10,
+                    help='Number of annular regions in fuel')
+parser.add_argument('-a', '--axial', type=int, default=196,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(clone=False, multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('core-depleted')
+    else:
+        directory = Path('core-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+if args.rings > 1:
+    ring_radii = np.sqrt(np.arange(1, args.rings)*pellet_OR**2 / args.rings)
+else:
+    ring_radii = None
+geometry = core_geometry(ring_radii, args.axial, args.depleted)
+
+h = active_fuel_length / args.axial
+fuel_mats = {}
+
+# Count the number of instances for each cell and material
+if args.clone:
+    geometry.determine_paths(instances_only=True)
+
+fuel_volume = pi * pellet_OR**2 * h / args.rings
+for cell in tqdm(geometry.get_all_cells().values(),
+                 desc='Differentiating materials / assigning volume'):
+    if cell.fill in materials:
+        # Determine if this material is fuel
+        name = cell.fill.name
+        is_fuel = 'UO2 Fuel' in name
+
+        # Determine volume of each fuel material
+        if is_fuel:
+            if args.clone:
+                # Fill cell with list of "differentiated" materials if requested
+                cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
+                for mat in cell.fill:
+                    mat.volume = fuel_volume
+            else:
+                r_o = cell.region.bounding_box[1][0]
+                if (name, r_o) not in fuel_mats:
+                    cell.fill = cell.fill.clone()
+                    cell.fill.volume = fuel_volume
+                    fuel_mats[name, r_o] = cell.fill
+                else:
+                    cell.fill = fuel_mats[name, r_o]
+        else:
+            cell.fill.volume = 1.0
+
+#### Create OpenMC "materials.xml" file
+all_materials = geometry.get_all_materials()
+materials = openmc.Materials(all_materials.values())
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
+upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 10000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+settings.temperature = {
+    'default': inlet_temperature,
+    'method': 'interpolation',
+    'range': (300.0, 1500.0),
+}
+if args.multipole:
+    settings.temperature['multipole'] = True
+    settings.temperature['tolerance'] = 1000
+
+settings.export_to_xml(str(directory / 'settings.xml'))

smr/build-core-long.py

@@ -0,0 +1,118 @@
+#!/usr/bin/env python3
+
+import argparse
+from math import pi, isclose
+from pathlib import Path
+
+import openmc
+from smr.materials import materials
+from smr.surfaces import bottom_fuel_stack, top_active_core, \
+    pellet_OR, pin_pitch, clad_IR, clad_OR, active_fuel_length
+from smr.core import core_geometry
+from smr import inlet_temperature
+import smr.surfaces
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', dest='multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('-a', '--axial', type=int, default=100,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('core-long-depleted')
+    else:
+        directory = Path('core-long-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+# Modify lattice pitch
+smr.surfaces.lattice_pitch = lattice_pitch = 17*smr.surfaces.pin_pitch
+
+ring_radii = [0.1*pin_pitch, 0.2*pin_pitch]
+
+geometry = core_geometry(ring_radii, args.axial, args.depleted)
+
+h = active_fuel_length / args.axial
+fuel_mats = {}
+
+for cell in geometry.get_all_cells().values():
+    if cell.fill in materials:
+        # Determine volume of each fuel material
+        name = cell.fill.name
+        if 'UO2 Fuel' in name:
+            upper_right = cell.region.bounding_box[1][0]
+            if isclose(upper_right, ring_radii[0]):
+                ri, ro = 0.0, ring_radii[0]
+            elif isclose(upper_right, ring_radii[1]):
+                ri, ro = ring_radii[0], ring_radii[1]
+            else:
+                ri, ro = ring_radii[1], pellet_OR
+            if (name, ri) not in fuel_mats:
+                cell.fill = cell.fill.clone()
+                cell.fill.volume = pi * (ro*ro - ri*ri) * h
+                fuel_mats[name, ri] = cell.fill
+            else:
+                cell.fill = fuel_mats[name, ri]
+        elif name == 'Helium':
+            cell.fill.volume = pi * (clad_IR**2 - pellet_OR**2) * h
+        elif name == 'M5':
+            # Clad is not subdivided
+            cell.fill.volume = pi * (clad_OR**2 - clad_IR**2) * active_fuel_length
+        else:
+            cell.fill.volume = 1.0
+
+
+#### Create OpenMC "materials.xml" file
+all_materials = geometry.get_all_materials()
+materials = openmc.Materials(all_materials.values())
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
+upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 20_000_000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+settings.temperature = {
+    'default': inlet_temperature,
+    'method': 'interpolation',
+    'range': (300.0, 1500.0),
+}
+if args.multipole:
+    settings.temperature['multipole'] = True
+    settings.temperature['tolerance'] = 1000
+
+settings.export_to_xml(str(directory / 'settings.xml'))
+
+# Check assembly power distribution
+core_lattice = geometry.get_cells_by_fill_name('Main core')[0].fill
+mesh = openmc.RegularMesh.from_rect_lattice(core_lattice)
+assembly_power = openmc.Tally()
+assembly_power.filters = [openmc.MeshFilter(mesh)]
+assembly_power.scores = ['nu-fission']
+tallies = openmc.Tallies([assembly_power])
+tallies.export_to_xml(directory / 'tallies.xml')

smr/build-core-short.py

@@ -0,0 +1,131 @@
+#!/usr/bin/env python3
+
+import argparse
+from math import pi, isclose
+from pathlib import Path
+
+import openmc
+from smr.materials import materials
+from smr.surfaces import bottom_fuel_stack, top_active_core, \
+    pellet_OR, surfs, pin_pitch, clad_IR, clad_OR
+import smr.surfaces
+import smr.pins
+from smr.core import core_geometry
+from smr import inlet_temperature
+
+# Define command-line options
+parser = argparse.ArgumentParser()
+parser.add_argument('--multipole', action='store_true',
+                    help='Use multipole cross sections')
+parser.add_argument('--no-multipole', action='store_false',
+                    help='Do not use multipole cross sections')
+parser.add_argument('-a', '--axial', type=int, default=3,
+                    help='Number of axial subdivisions in fuel')
+parser.add_argument('-d', '--depleted', action='store_true',
+                    help='Whether UO2 compositions should represent depleted fuel')
+parser.add_argument('-o', '--output-dir', type=Path, default=None)
+parser.set_defaults(multipole=True)
+args = parser.parse_args()
+
+# Make directory for inputs
+if args.output_dir is None:
+    if args.depleted:
+        directory = Path('core-short-depleted')
+    else:
+        directory = Path('core-short-fresh')
+else:
+    directory = args.output_dir
+directory.mkdir(exist_ok=True)
+
+# Modify lattice pitch
+smr.surfaces.lattice_pitch = lattice_pitch = 17*smr.surfaces.pin_pitch
+
+# Modify fuel length
+length = 3. * pin_pitch
+smr.surfaces.active_fuel_length = length
+smr.pins.top_active_core = length
+surfs['top active core'].z0 = length
+
+# Change top and bottom of model to contain only fuel
+surfs['lower bound'].z0 = 0.0
+surfs['lower bound'].boundary_type = 'reflective'
+surfs['upper bound'].z0 = length
+surfs['upper bound'].boundary_type = 'reflective'
+
+ring_radii = [0.1*pin_pitch, 0.2*pin_pitch]
+
+geometry = core_geometry(ring_radii, args.axial, args.depleted)
+
+h = length / args.axial
+fuel_mats = {}
+
+for cell in geometry.get_all_cells().values():
+    if cell.fill in materials:
+        # Determine volume of each fuel material
+        name = cell.fill.name
+        if 'UO2 Fuel' in name:
+            upper_right = cell.region.bounding_box[1][0]
+            if isclose(upper_right, ring_radii[0]):
+                ri, ro = 0.0, ring_radii[0]
+            elif isclose(upper_right, ring_radii[1]):
+                ri, ro = ring_radii[0], ring_radii[1]
+            else:
+                ri, ro = ring_radii[1], pellet_OR
+            if (name, ri) not in fuel_mats:
+                cell.fill = cell.fill.clone()
+                cell.fill.volume = pi * (ro*ro - ri*ri) * h
+                fuel_mats[name, ri] = cell.fill
+            else:
+                cell.fill = fuel_mats[name, ri]
+        elif name == 'Helium':
+            cell.fill.volume = pi * (clad_IR**2 - pellet_OR**2) * h
+        elif name == 'M5':
+            # Clad is not subdivided
+            cell.fill.volume = pi * (clad_OR**2 - clad_IR**2) * length
+        else:
+            cell.fill.volume = 1.0
+
+
+#### Create OpenMC "materials.xml" file
+all_materials = geometry.get_all_materials()
+materials = openmc.Materials(all_materials.values())
+materials.export_to_xml(str(directory / 'materials.xml'))
+
+#### Create OpenMC "geometry.xml" file
+geometry.export_to_xml(str(directory / 'geometry.xml'))
+
+
+#### Create OpenMC "settings.xml" file
+
+# Construct uniform initial source distribution over fissionable zones
+lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
+upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
+source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
+source.space.only_fissionable = True
+
+settings = openmc.Settings()
+settings.batches = 200
+settings.inactive = 100
+settings.particles = 10000
+settings.output = {'tallies': False, 'summary': False}
+settings.source = source
+settings.sourcepoint = {'write': False}
+settings.temperature = {
+    'default': inlet_temperature,
+    'method': 'interpolation',
+    'range': (300.0, 1500.0),
+}
+if args.multipole:
+    settings.temperature['multipole'] = True
+    settings.temperature['tolerance'] = 1000
+
+settings.export_to_xml(str(directory / 'settings.xml'))
+
+# Check assembly power distribution
+core_lattice = geometry.get_cells_by_fill_name('Main core')[0].fill
+mesh = openmc.RegularMesh.from_rect_lattice(core_lattice)
+assembly_power = openmc.Tally()
+assembly_power.filters = [openmc.MeshFilter(mesh)]
+assembly_power.scores = ['nu-fission']
+tallies = openmc.Tallies([assembly_power])
+tallies.export_to_xml(directory / 'tallies.xml')

smr/build-depleted.py

@@ -1,150 +0,0 @@
-from collections import OrderedDict, defaultdict
-import copy
-import os
-
-import numpy as np
-import openmc
-import opendeplete
-
-from smr.materials import materials
-from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
-from smr.core import geometry
-
-#### Create "dummy" inputs to export distribcell paths for burnable cells
-
-# Create OpenMC "geometry.xml" file
-geometry.export_to_xml()
-
-# Create OpenMC "materials.xml" file
-materials.export_to_xml()
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
-upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-# Create OpenMC "settings.xml" file
-settings = openmc.Settings()
-settings.batches = 2
-settings.inactive = 1
-settings.particles = 10
-settings.output = {'tallies': False}
-settings.source = source
-settings.sourcepoint_write = False
-settings.export_to_xml()
-
-#  Create OpenMC "tallies.xml" file
-tallies = openmc.Tallies()
-fuel_cells = geometry.get_cells_by_name(
-    name='(1.6%) (0)', case_sensitive=True)
-fuel_cells.extend(geometry.get_cells_by_name(
-    name='(2.4%) (0)', case_sensitive=True))
-fuel_cells.extend(geometry.get_cells_by_name(
-    name='(3.1%) (0)', case_sensitive=True))
-
-# Instantiate a "dummy" distribcell tally for each cell we wish to deplete
-for cell in fuel_cells:
-    tally = openmc.Tally(name='dummy distribcell tally')
-    distribcell_filter = openmc.DistribcellFilter([cell.id])
-    tally.filters = [distribcell_filter]
-    tally.scores = ['fission']
-    tallies.append(tally)
-
-tallies.export_to_xml()
-
-# Run OpenMC to generate summary.h5 file
-openmc.run()
-
-# Open "summary.h5" file
-su = openmc.Summary('summary.h5')
-fuel_cells = su.openmc_geometry.get_cells_by_name(
-    name='(1.6%) (0)', case_sensitive=True)
-fuel_cells.extend(su.openmc_geometry.get_cells_by_name(
-    name='(2.4%) (0)', case_sensitive=True))
-fuel_cells.extend(su.openmc_geometry.get_cells_by_name(
-    name='(3.1%) (0)', case_sensitive=True))
-
-
-#### Setup OpenDeplete Materials wrapper
-
-materials = opendeplete.Materials()
-materials.temperature = OrderedDict()
-materials.sab = OrderedDict()
-materials.initial_density = OrderedDict()
-materials.burn = OrderedDict()
-materials.cross_sections = os.environ["OPENMC_CROSS_SECTIONS"]
-
-# Extract cell materials, temperatures and sab
-for cell in su.openmc_geometry.get_all_material_cells():
-    materials.burn[cell.name] = 'fuel' in cell.fill.name.lower()
-    materials.temperature[cell.name] = cell.temperature[0]
-    if len(cell.fill._sab) > 0:
-        materials.sab[cell.name] = cell.fill._sab[0]
-
-# Extract initial fuel nuclide densities in units of at/cc
-for cell in fuel_cells:
-    densities = cell.fill.get_nuclide_atom_densities()
-    materials.initial_density[cell.fill.name] = OrderedDict()
-
-    # Convert atom densities from at/b-cm to at/cc
-    for nuclide in densities:
-        materials.initial_density[cell.fill.name][nuclide.name] = \
-            densities[nuclide][1] * 1e24
-
-# Determine the maximum material ID
-all_mats = su.openmc_geometry.get_all_materials()
-max_material_id = 0
-for material in all_mats:
-    max_material_id = max(max_material_id, material.id)
-
-# FIXME: Automatically extract info needed to calculate burnable cell volumes
-# Fuel rod geometric parameters
-radius = 0.39218
-height = 5.
-
-# Use defaultdict since OpenDeplete assumes volumes specified for all cells
-volumes = defaultdict(lambda: 1)
-
-# Assign distribmats for each material
-for cell in fuel_cells:
-    new_materials = []
-    num_instances = len(cell.distribcell_paths)
-
-    for i in range(num_instances):
-        new_material = copy.deepcopy(cell.fill)
-        new_material.id = max_material_id + 1
-        max_material_id += 1
-        new_materials.append(new_material)
-
-        # Store volume of burnable fuel rods cells
-        volumes[new_material.id] =  np.pi * radius**2 * height
-
-    cell.fill = new_materials
-
-# Create dt vector for 1 month with 15 day timesteps
-dt1 = 15*24*60*60  # 15 days
-dt2 = 1.*30*24*60*60  # 1 months
-N = np.floor(dt2/dt1)
-dt = np.repeat([dt1], N)
-
-# Create settings variable
-settings = opendeplete.Settings()
-
-settings.openmc_call = ["mpirun", "openmc"]
-settings.particles = 1000000
-settings.batches = 200
-settings.inactive = 100
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [15, 15, 1]
-
-settings.power = 2.337e15 * ((17.*17.*37.) / 1.5**2)  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'depleted'
-
-op = opendeplete.Operator()
-op.geometry_fill(su.openmc_geometry, volumes, materials, settings)
-
-# Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrate(op, opendeplete.ce_cm_c1)

smr/build-fresh.py

@@ -1,124 +0,0 @@
-import os
-import shutil
-
-import numpy as np
-
-import openmc
-from smr.materials import materials
-from smr.plots import plots
-from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
-from smr.core import geometry
-
-
-#### Create OpenMC "geometry.xml" file
-geometry.export_to_xml()
-
-
-#### Create OpenMC "materials.xml" file
-materials.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = (multipole == 'y')
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
-upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings = openmc.Settings()
-settings.batches = 200
-settings.inactive = 100
-settings.particles = 10000
-settings.output = {'tallies': False}
-settings.source = source
-settings.sourcepoint_write = False
-
-if multipole:
-    settings.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-plots.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 8-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([0., 0.058e-6, 0.14e-6, 0.28e-6,
-                                      0.625e-6, 4.e-6, 5.53e-3, 821.e-3, 20.])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [7*17, 7*17, 100]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= (7*17)
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()
-
-
-#### Move all XML files to 'fresh' directory
-
-if not os.path.exists('fresh'):
-    os.makedirs('fresh')
-    
-shutil.move('materials.xml', 'fresh/materials.xml')
-shutil.move('geometry.xml', 'fresh/geometry.xml')
-shutil.move('settings.xml', 'fresh/setting.xml')
-shutil.move('tallies.xml', 'fresh/tallies.xml')
-shutil.move('plots.xml', 'fresh/plots.xml')

smr/build-xml.py

@@ -1,109 +0,0 @@
-import numpy as np
-
-import openmc
-from smr.materials import materials
-from smr.plots import plots
-from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
-from smr.core import geometry
-
-
-#### Create OpenMC "geometry.xml" file
-geometry.export_to_xml()
-
-
-#### Create OpenMC "materials.xml" file
-materials.export_to_xml()
-
-
-#### Create OpenMC "settings.xml" file
-
-# Query the user on whether to use multipole cross sections
-multipole = input('Use multipole cross sections? (y/n): ').lower()
-multipole = (multipole == 'y')
-
-# Construct uniform initial source distribution over fissionable zones
-lower_left = [-7.*lattice_pitch/2., -7.*lattice_pitch/2., bottom_fuel_stack]
-upper_right = [+7.*lattice_pitch/2., +7.*lattice_pitch/2., top_active_core]
-source = openmc.source.Source(space=openmc.stats.Box(lower_left, upper_right))
-source.space.only_fissionable = True
-
-settings = openmc.Settings()
-settings.batches = 200
-settings.inactive = 100
-settings.particles = 10000
-settings.output = {'tallies': False}
-settings.source = source
-settings.sourcepoint_write = False
-
-if multipole:
-    settings.temperature = {'multipole': True, 'tolerance': 1000}
-
-settings.export_to_xml()
-
-
-#### Create OpenMC "plots.xml" file
-plots.export_to_xml()
-
-
-#### Create OpenMC MGXS libraries
-
-# Get all cells filled with a "fuel" material
-mat_cells = geometry.get_all_material_cells()
-fuel_cells = []
-for cell in mat_cells:
-    if 'fuel' in cell.fill.name.lower():
-        fuel_cells.append(cell)
-
-# CASMO 8-group structure
-energy_groups = openmc.mgxs.EnergyGroups()
-energy_groups.group_edges = np.array([0., 0.058e-6, 0.14e-6, 0.28e-6,
-                                      0.625e-6, 4.e-6, 5.53e-3, 821.e-3, 20.])
-
-# Initialize a 70-group "distribcell" MGXS library
-cell_mgxs_lib = openmc.mgxs.Library(geometry, by_nuclide=True)
-cell_mgxs_lib.energy_groups = energy_groups
-cell_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-cell_mgxs_lib.domain_type = 'distribcell'
-cell_mgxs_lib.domains = fuel_cells
-cell_mgxs_lib.correction = None
-cell_mgxs_lib.build_library()
-
-# Initialize a 70-group "material" MGXS library
-mat_mgxs_lib = openmc.mgxs.Library(geometry, by_nuclide=True)
-mat_mgxs_lib.energy_groups = energy_groups
-mat_mgxs_lib.mgxs_types = ['total', 'nu-fission', 'nu-scatter matrix', 'chi']
-mat_mgxs_lib.domain_type = 'material'
-mat_mgxs_lib.correction = None
-mat_mgxs_lib.build_library()
-
-
-####  Create mesh tallies for verification of pin-wise reaction rates
-
-# Instantiate a tally Mesh
-mesh = openmc.Mesh(name='assembly mesh')
-mesh.type = 'regular'
-mesh.dimension = [7*17, 7*17, 100]
-mesh.lower_left = lower_left
-mesh.width = (np.array(upper_right) - np.array(lower_left))
-mesh.width[:2] /= (7*17)
-mesh_filter = openmc.MeshFilter(mesh)
-
-# Instantiate energy-integrated fission rate mesh Tally
-fission_rates = openmc.Tally(name='fission rates')
-fission_rates.filters = [mesh_filter]
-fission_rates.scores = ['fission']
-
-# Instantiate energy-wise U-238 capture rate mesh Tally
-capture_rates = openmc.Tally(name='u-238 capture')
-capture_rates.filters = [mesh_filter]
-capture_rates.nuclides = ['U238']
-capture_rates.scores = ['absorption', 'fission']
-
-
-####  Create OpenMC "tallies.xml" file
-
-# Create a "tallies.xml" file for the mesh tallies
-tallies_file = openmc.Tallies([fission_rates, capture_rates])
-cell_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-mat_mgxs_lib.add_to_tallies_file(tallies_file, merge=True)
-tallies_file.export_to_xml()

smr/core-depleted/settings.xml

@@ -1,14 +1,13 @@
 <?xml version='1.0' encoding='utf-8'?>
 <settings>
-    <eigenvalue>
-        <particles>1000000</particles>
-        <batches>200</batches>
-        <inactive>100</inactive>
-    </eigenvalue>
+    <run_mode>eigenvalue</run_mode>
+    <particles>1000000</particles>
+    <batches>200</batches>
+    <inactive>100</inactive>
     <source strength="1.0">
         <space type="box">
             <parameters>-75.26274000000001 -75.26274000000001 36.007 75.26274000000001 75.26274000000001 236.007</parameters>
         </space>
     </source>
-    <seed>3493073714866283028</seed>
+    <seed>5079492714264831673</seed>
 </settings>

smr/core-fresh/materials.xml

@@ -0,0 +1,214 @@
+<?xml version='1.0' encoding='utf-8'?>
+<materials>
+  <material id="1" name="Helium">
+    <temperature>300</temperature>
+    <density units="g/cc" value="0.0015981" />
+    <nuclide ao="2e-06" name="He3" />
+    <nuclide ao="0.999998" name="He4" />
+  </material>
+  <material id="2" name="Air">
+    <temperature>300</temperature>
+    <density units="g/cc" value="0.00616" />
+    <nuclide ao="0.2094205995" name="O16" />
+    <nuclide ao="7.94005e-05" name="O17" />
+    <nuclide ao="0.7780395633" name="N14" />
+    <nuclide ao="0.0028604367000000003" name="N15" />
+    <nuclide ao="3.1124879999999996e-05" name="Ar36" />
+    <nuclide ao="5.86857e-06" name="Ar38" />
+    <nuclide ao="0.00929300655" name="Ar40" />
+    <nuclide ao="0.00027" name="C0" />
+  </material>
+  <material id="3" name="Inconel">
+    <temperature>300</temperature>
+    <density units="g/cc" value="8.2" />
+    <nuclide name="Si28" wo="0.003215573104901967" />
+    <nuclide name="Si29" wo="0.00016911126024954278" />
+    <nuclide name="Si30" wo="0.00011531563484849038" />
+    <nuclide name="Cr50" wo="0.007913309553017726" />
+    <nuclide name="Cr52" wo="0.15869399115925625" />
+    <nuclide name="Cr53" wo="0.018341120727338085" />
+    <nuclide name="Cr54" wo="0.004651578560387908" />
+    <nuclide name="Mn55" wo="0.0087" />
+    <nuclide name="Fe54" wo="0.016163233201258693" />
+    <nuclide name="Fe56" wo="0.26311407687664323" />
+    <nuclide name="Fe57" wo="0.006185135350045743" />
+    <nuclide name="Fe58" wo="0.0008375545720523535" />
+    <nuclide name="Ni58" wo="0.34398505352691505" />
+    <nuclide name="Ni60" wo="0.1370661540479713" />
+    <nuclide name="Ni61" wo="0.006057615154415727" />
+    <nuclide name="Ni62" wo="0.01963045531316453" />
+    <nuclide name="Ni64" wo="0.005160721957533462" />
+  </material>
+  <material id="4" name="SS304">
+    <temperature>300</temperature>
+    <density units="g/cc" value="8.03" />
+    <nuclide name="Si28" wo="0.005512411036974801" />
+    <nuclide name="Si29" wo="0.0002899050175706448" />
+    <nuclide name="Si30" wo="0.00019768394545455493" />
+    <nuclide name="Cr50" wo="0.007930004298910168" />
+    <nuclide name="Cr52" wo="0.15902878860895933" />
+    <nuclide name="Cr53" wo="0.018379815074864116" />
+    <nuclide name="Cr54" wo="0.004661392017266364" />
+    <nuclide name="Mn55" wo="0.02" />
+    <nuclide name="Fe54" wo="0.03861561826636726" />
+    <nuclide name="Fe56" wo="0.6286064568062312" />
+    <nuclide name="Fe57" wo="0.014776921339264018" />
+    <nuclide name="Fe58" wo="0.002001003588137652" />
+    <nuclide name="Ni58" wo="0.06719770531879568" />
+    <nuclide name="Ni60" wo="0.02677596289274688" />
+    <nuclide name="Ni61" wo="0.0011833590846680462" />
+    <nuclide name="Ni62" wo="0.0038348222920813694" />
+    <nuclide name="Ni64" wo="0.0010081504117080411" />
+  </material>
+  <material id="5" name="Carbon Steel">
+    <temperature>300</temperature>
+    <density units="g/cc" value="7.8" />
+    <nuclide name="C0" wo="0.0027" />
+    <nuclide name="Mn55" wo="0.0075" />
+    <nuclide name="P31" wo="0.00025" />
+    <nuclide name="S32" wo="0.00023692152702311576" />
+    <nuclide name="S33" wo="1.924704844422474e-06" />
+    <nuclide name="S34" wo="1.1112880999711348e-05" />
+    <nuclide name="S36" wo="4.088713275043879e-08" />
+    <nuclide name="Si28" wo="0.0036749406913165338" />
+    <nuclide name="Si29" wo="0.00019327001171376318" />
+    <nuclide name="Si30" wo="0.0001317892969697033" />
+    <nuclide name="Ni58" wo="0.005039827898909675" />
+    <nuclide name="Ni60" wo="0.002008197216956016" />
+    <nuclide name="Ni61" wo="8.875193135010345e-05" />
+    <nuclide name="Ni62" wo="0.00028761167190610265" />
+    <nuclide name="Ni64" wo="7.561128087810308e-05" />
+    <nuclide name="Cr50" wo="0.00014607902655887153" />
+    <nuclide name="Cr52" wo="0.0029294776849018824" />
+    <nuclide name="Cr53" wo="0.00033857554085276" />
+    <nuclide name="Cr54" wo="8.586774768648565e-05" />
+    <nuclide name="Mo100" wo="0.0006341263666702117" />
+    <nuclide name="Mo92" wo="0.0008769932056639445" />
+    <nuclide name="Mo94" wo="0.0005619573981472699" />
+    <nuclide name="Mo95" wo="0.0009812790231824658" />
+    <nuclide name="Mo96" wo="0.0010415835207694215" />
+    <nuclide name="Mo97" wo="0.0006048497176301975" />
+    <nuclide name="Mo98" wo="0.00154921076793649" />
+    <nuclide name="V50" wo="1.2256016778573164e-06" />
+    <nuclide name="V51" wo="0.0004987743983221427" />
+    <nuclide name="Nb93" wo="0.0001" />
+    <nuclide name="Cu63" wo="0.001369583906732317" />
+    <nuclide name="Cu65" wo="0.0006304160932676829" />
+    <nuclide name="Ca40" wo="0.00014499268968855714" />
+    <nuclide name="Ca42" wo="1.0160391170196e-06" />
+    <nuclide name="Ca43" wo="2.1705537495761849e-07" />
+    <nuclide name="Ca44" wo="3.4317237524995553e-06" />
+    <nuclide name="Ca46" wo="6.8796341950755285e-09" />
+    <nuclide name="Ca48" wo="3.3561243277098485e-07" />
+    <nuclide name="B10" wo="5.506648724403529e-06" />
+    <nuclide name="B11" wo="2.449335127559647e-05" />
+    <nuclide name="Ti46" wo="1.1880142852196743e-05" />
+    <nuclide name="Ti47" wo="1.0946673488791549e-05" />
+    <nuclide name="Ti48" wo="0.00011076757837453494" />
+    <nuclide name="Ti49" wo="8.298285799079257e-06" />
+    <nuclide name="Ti50" wo="8.107319485397494e-06" />
+    <nuclide name="Al27" wo="0.00025" />
+    <nuclide name="Fe54" wo="0.054472297655949964" />
+    <nuclide name="Fe56" wo="0.8867302806705092" />
+    <nuclide name="Fe57" wo="0.020844748673414723" />
+    <nuclide name="Fe58" wo="0.0028226730001262813" />
+  </material>
+  <material id="6" name="Zircaloy-4">
+    <temperature>300</temperature>
+    <density units="g/cc" value="6.55" />
+    <nuclide name="O16" wo="0.0012494965182849112" />
+    <nuclide name="O17" wo="5.034817150887735e-07" />
+    <nuclide name="Cr50" wo="4.1736864731106146e-05" />
+    <nuclide name="Cr52" wo="0.0008369936242576807" />
+    <nuclide name="Cr53" wo="9.673586881507429e-05" />
+    <nuclide name="Cr54" wo="2.4533642196138756e-05" />
+    <nuclide name="Fe54" wo="0.00011855672274761877" />
+    <nuclide name="Fe56" wo="0.001929932104229657" />
+    <nuclide name="Fe57" wo="4.536774095388075e-05" />
+    <nuclide name="Fe58" wo="6.143432068843669e-06" />
+    <nuclide name="Zr90" wo="0.49750307249921255" />
+    <nuclide name="Zr91" wo="0.10970127796055709" />
+    <nuclide name="Zr92" wo="0.16952409354767467" />
+    <nuclide name="Zr94" wo="0.17553856942304608" />
+    <nuclide name="Zr96" wo="0.02888298656950975" />
+    <nuclide name="Sn112" wo="0.0001325869644430062" />
+    <nuclide name="Sn114" wo="9.182449637587617e-05" />
+    <nuclide name="Sn115" wo="4.771905922545867e-05" />
+    <nuclide name="Sn116" wo="0.002058423153629443" />
+    <nuclide name="Sn117" wo="0.0010966473429083066" />
+    <nuclide name="Sn118" wo="0.0034879812938438245" />
+    <nuclide name="Sn119" wo="0.001247577110245757" />
+    <nuclide name="Sn120" wo="0.004771539495238715" />
+    <nuclide name="Sn122" wo="0.0006894094798456136" />
+    <nuclide name="Sn124" wo="0.000876291604244001" />
+  </material>
+  <material id="7" name="Ag-In-Cd">
+    <temperature>300</temperature>
+    <density units="g/cc" value="10.16" />
+    <nuclide name="Ag107" wo="0.4110094082785408" />
+    <nuclide name="Ag109" wo="0.3889905917214592" />
+    <nuclide name="In113" wo="0.006314443289265887" />
+    <nuclide name="In115" wo="0.1436855567107341" />
+    <nuclide name="Cd106" wo="0.0005864650126662538" />
+    <nuclide name="Cd108" wo="0.0004261883300584398" />
+    <nuclide name="Cd110" wo="0.006095738560062021" />
+    <nuclide name="Cd111" wo="0.006311586256788057" />
+    <nuclide name="Cd112" wo="0.011999697873295025" />
+    <nuclide name="Cd113" wo="0.006140180186664414" />
+    <nuclide name="Cd114" wo="0.01456750341101345" />
+    <nuclide name="Cd116" wo="0.00387264036945234" />
+  </material>
+  <material id="8" name="Borated Water">
+    <temperature>300</temperature>
+    <density units="g/cc" value="0.7405820675158279" />
+    <nuclide ao="0.00032178659941803253" name="B10" />
+    <nuclide ao="0.0013017583017829388" name="B11" />
+    <nuclide ao="1.996441935899364" name="H1" />
+    <nuclide ao="0.0003109742982341739" name="H2" />
+    <nuclide ao="0.9979980704223166" name="O16" />
+    <nuclide ao="0.0003783846764824448" name="O17" />
+    <sab name="c_H_in_H2O" />
+  </material>
+  <material id="9" name="Borosilicate Glass">
+    <temperature>300</temperature>
+    <density units="g/cc" value="2.26" />
+    <nuclide ao="0.6509787013744828" name="O16" />
+    <nuclide ao="0.00024681447050525047" name="O17" />
+    <nuclide ao="0.23640592474731761" name="Si28" />
+    <nuclide ao="0.01200401834354893" name="Si29" />
+    <nuclide ao="0.007913102535354443" name="Si30" />
+    <nuclide ao="0.024236195272461444" name="Al27" />
+    <nuclide ao="0.012259454378427138" name="B10" />
+    <nuclide ao="0.06018253698401973" name="B11" />
+  </material>
+  <material id="10" name="1.6% Enr. UO2 Fuel">
+    <temperature>300</temperature>
+    <density units="g/cc" value="10.31341" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+    <nuclide ao="0.00014571996318473284" name="U234" />
+    <nuclide ao="0.01630316269333107" name="U235" />
+    <nuclide ao="0.983476441027697" name="U238" />
+    <nuclide ao="7.467631578722921e-05" name="U236" />
+  </material>
+  <material id="11" name="2.4% Enr. UO2 Fuel">
+    <temperature>300</temperature>
+    <density units="g/cc" value="10.29748" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+    <nuclide ao="0.00021718560529202018" name="U234" />
+    <nuclide ao="0.024298745211983164" name="U235" />
+    <nuclide ao="0.9753727692586048" name="U238" />
+    <nuclide ao="0.00011129992411998257" name="U236" />
+  </material>
+  <material id="12" name="3.1% Enr. UO2 Fuel">
+    <temperature>300</temperature>
+    <density units="g/cc" value="10.30166" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+    <nuclide ao="0.0002807139975428889" name="U234" />
+    <nuclide ao="0.03140630749703991" name="U235" />
+    <nuclide ao="0.9681691225321637" name="U238" />
+    <nuclide ao="0.00014385597325352966" name="U236" />
+  </material>
+</materials>

smr/core-fresh/plots.xml

@@ -0,0 +1,92 @@
+<?xml version='1.0' encoding='utf-8'?>
+<plots>
+  <!--radial slice -->
+  <plot basis="xy" color_by="material" filename="radial_xy_slice" id="1" type="slice">
+    <origin>0.0 0.0 141.61599999999999</origin>
+    <width>268.79549999999995 268.79549999999995</width>
+    <pixels>1000 1000</pixels>
+    <background>255 255 255</background>
+    <color id="1" rgb="255 218 185" />
+    <color id="2" rgb="255 255 255" />
+    <color id="3" rgb="101 101 101" />
+    <color id="4" rgb="0 0 0" />
+    <color id="5" rgb="0 0 0" />
+    <color id="6" rgb="201 201 201" />
+    <color id="7" rgb="255 0 0" />
+    <color id="8" rgb="198 226 255" />
+    <color id="9" rgb="0 255 0" />
+    <color id="10" rgb="142 35 35" />
+    <color id="11" rgb="255 215 0" />
+    <color id="12" rgb="0 0 128" />
+  </plot>
+  <!--axial slice-->
+  <plot basis="xz" color_by="material" filename="axial_xz_slice" id="2" type="slice">
+    <origin>0.0 0.0 141.61599999999999</origin>
+    <width>270.0 283.23199999999997</width>
+    <pixels>1000 1000</pixels>
+    <background>255 255 255</background>
+    <color id="1" rgb="255 218 185" />
+    <color id="2" rgb="255 255 255" />
+    <color id="3" rgb="101 101 101" />
+    <color id="4" rgb="0 0 0" />
+    <color id="5" rgb="0 0 0" />
+    <color id="6" rgb="201 201 201" />
+    <color id="7" rgb="255 0 0" />
+    <color id="8" rgb="198 226 255" />
+    <color id="9" rgb="0 255 0" />
+    <color id="10" rgb="142 35 35" />
+    <color id="11" rgb="255 215 0" />
+    <color id="12" rgb="0 0 128" />
+  </plot>
+  <!--assembly grid spacer-->
+  <plot basis="xy" color_by="material" filename="assm_grid_spacer" id="3" type="slice">
+    <origin>0.0 0.0 95.0</origin>
+    <width>32.25546 32.25546</width>
+    <pixels>2000 2000</pixels>
+    <background>255 255 255</background>
+    <color id="1" rgb="255 218 185" />
+    <color id="2" rgb="255 255 255" />
+    <color id="3" rgb="101 101 101" />
+    <color id="4" rgb="0 0 0" />
+    <color id="5" rgb="0 0 0" />
+    <color id="6" rgb="201 201 201" />
+    <color id="7" rgb="255 0 0" />
+    <color id="8" rgb="198 226 255" />
+    <color id="9" rgb="0 255 0" />
+    <color id="10" rgb="142 35 35" />
+    <color id="11" rgb="255 215 0" />
+    <color id="12" rgb="0 0 128" />
+  </plot>
+  <!--assembly no spacer-->
+  <plot basis="xy" color_by="material" filename="assm_no_spacer" id="4" type="slice">
+    <origin>0.0 0.0 90.0</origin>
+    <width>32.25546 32.25546</width>
+    <pixels>2000 2000</pixels>
+    <background>255 255 255</background>
+    <color id="1" rgb="255 218 185" />
+    <color id="2" rgb="255 255 255" />
+    <color id="3" rgb="101 101 101" />
+    <color id="4" rgb="0 0 0" />
+    <color id="5" rgb="0 0 0" />
+    <color id="6" rgb="201 201 201" />
+    <color id="7" rgb="255 0 0" />
+    <color id="8" rgb="198 226 255" />
+    <color id="9" rgb="0 255 0" />
+    <color id="10" rgb="142 35 35" />
+    <color id="11" rgb="255 215 0" />
+    <color id="12" rgb="0 0 128" />
+  </plot>
+  <!--assembly no spacer cell-->
+  <plot basis="xy" color_by="cell" filename="assm_no_spacer_cell" id="5" type="slice">
+    <origin>0.0 0.0 90.0</origin>
+    <width>32.25546 32.25546</width>
+    <pixels>2000 2000</pixels>
+    <background>255 255 255</background>
+  </plot>
+  <!--z slice-->
+  <plot basis="xz" color_by="cell" filename="assm_xz" id="6" type="slice">
+    <origin>0.0 0.0 141.61599999999999</origin>
+    <width>32.25546 283.23199999999997</width>
+    <pixels>455 4000</pixels>
+  </plot>
+</plots>

smr/core-fresh/settings.xml

@@ -0,0 +1,15 @@
+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>eigenvalue</run_mode>
+  <particles>10000</particles>
+  <batches>200</batches>
+  <inactive>100</inactive>
+  <source strength="1.0">
+    <space type="fission">
+      <parameters>-75.26274 -75.26274 36.007 75.26274 75.26274 236.0066</parameters>
+    </space>
+  </source>
+  <output>
+    <tallies>false</tallies>
+  </output>
+</settings>

smr/fresh/geometry.xml

@@ -1,780 +0,0 @@
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-    <surface coeffs="252.564" id="10051" name="top upper nozzle" type="z-plane" />
-    <surface coeffs="786.348" id="10068" name="CR bank D top" type="z-plane" />
-    <surface coeffs="405.713" id="10069" name="CR bank D bottom" type="z-plane" />
-    <surface coeffs="0.0 0.0 85.0" id="10070" name="core barrel IR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 90.0" id="10071" name="core barrel OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 92.0" id="10072" name="neutron shield OR" type="z-cylinder" />
-    <surface coeffs="1.0 1.7320508075688767 0.0 0.0" id="10073" name="neutron shield NWbot SEtop" type="plane" />
-    <surface coeffs="1.0 0.5773502691896257 0.0 0.0" id="10074" name="neutron shield NWtop SEbot" type="plane" />
-    <surface coeffs="1.0 -1.7320508075688767 0.0 0.0" id="10075" name="neutron shield NEbot SWtop" type="plane" />
-    <surface coeffs="1.0 -0.5773502691896257 0.0 0.0" id="10076" name="neutron shield NEtop SWbot" type="plane" />
-    <surface coeffs="0.0 0.0 120.0" id="10077" name="RPV IR" type="z-cylinder" />
-    <surface boundary="vacuum" coeffs="0.0 0.0 135.0" id="10078" name="RPV OR" type="z-cylinder" />
-    <surface boundary="vacuum" coeffs="272.564" id="10079" name="upper problem boundary" type="z-plane" />
-    <surface boundary="vacuum" coeffs="0.0" id="10080" name="lower problem boundary" type="z-plane" />
-    <surface coeffs="3.15341" id="10081" name="baffle north" type="y-plane" />
-    <surface coeffs="-3.15341" id="10082" name="baffle south" type="y-plane" />
-    <surface coeffs="3.15341" id="10083" name="baffle east" type="x-plane" />
-    <surface coeffs="-3.15341" id="10084" name="baffle west" type="x-plane" />
-</geometry>

smr/fresh/materials.xml

@@ -1,211 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<materials>
-    <material id="10000" name="Helium">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.0015981" />
-        <nuclide ao="2e-06" name="He3" />
-        <nuclide ao="0.999998" name="He4" />
-    </material>
-    <material id="10001" name="Air">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.00616" />
-        <nuclide ao="0.2094205995" name="O16" />
-        <nuclide ao="7.94005e-05" name="O17" />
-        <nuclide ao="0.7780395633" name="N14" />
-        <nuclide ao="0.0028604367000000003" name="N15" />
-        <nuclide ao="3.1124879999999996e-05" name="Ar36" />
-        <nuclide ao="5.86857e-06" name="Ar38" />
-        <nuclide ao="0.00929300655" name="Ar40" />
-        <nuclide ao="0.00027" name="C0" />
-    </material>
-    <material id="10002" name="Inconel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.2" />
-        <nuclide name="Si28" wo="0.003215573104901967" />
-        <nuclide name="Si29" wo="0.00016911126024954278" />
-        <nuclide name="Si30" wo="0.00011531563484849038" />
-        <nuclide name="Cr50" wo="0.007913309553017726" />
-        <nuclide name="Cr52" wo="0.15869399115925625" />
-        <nuclide name="Cr53" wo="0.018341120727338085" />
-        <nuclide name="Cr54" wo="0.004651578560387908" />
-        <nuclide name="Mn55" wo="0.0087" />
-        <nuclide name="Fe54" wo="0.016163233201258693" />
-        <nuclide name="Fe56" wo="0.26311407687664323" />
-        <nuclide name="Fe57" wo="0.006185135350045743" />
-        <nuclide name="Fe58" wo="0.0008375545720523535" />
-        <nuclide name="Ni58" wo="0.34398505352691505" />
-        <nuclide name="Ni60" wo="0.1370661540479713" />
-        <nuclide name="Ni61" wo="0.006057615154415727" />
-        <nuclide name="Ni62" wo="0.01963045531316453" />
-        <nuclide name="Ni64" wo="0.005160721957533462" />
-    </material>
-    <material id="10003" name="SS304">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.03" />
-        <nuclide name="Si28" wo="0.005512411036974801" />
-        <nuclide name="Si29" wo="0.0002899050175706448" />
-        <nuclide name="Si30" wo="0.00019768394545455493" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719770531879568" />
-        <nuclide name="Ni60" wo="0.02677596289274688" />
-        <nuclide name="Ni61" wo="0.0011833590846680462" />
-        <nuclide name="Ni62" wo="0.0038348222920813694" />
-        <nuclide name="Ni64" wo="0.0010081504117080411" />
-    </material>
-    <material id="10004" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
-        <nuclide name="P31" wo="0.00025" />
-        <nuclide name="S32" wo="0.00023692152702311576" />
-        <nuclide name="S33" wo="1.924704844422474e-06" />
-        <nuclide name="S34" wo="1.1112880999711348e-05" />
-        <nuclide name="S36" wo="4.088713275043879e-08" />
-        <nuclide name="Si28" wo="0.0036749406913165338" />
-        <nuclide name="Si29" wo="0.00019327001171376318" />
-        <nuclide name="Si30" wo="0.0001317892969697033" />
-        <nuclide name="Ni58" wo="0.005039827898909675" />
-        <nuclide name="Ni60" wo="0.002008197216956016" />
-        <nuclide name="Ni61" wo="8.875193135010345e-05" />
-        <nuclide name="Ni62" wo="0.00028761167190610265" />
-        <nuclide name="Ni64" wo="7.561128087810308e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006341263666702117" />
-        <nuclide name="Mo92" wo="0.0008769932056639445" />
-        <nuclide name="Mo94" wo="0.0005619573981472699" />
-        <nuclide name="Mo95" wo="0.0009812790231824658" />
-        <nuclide name="Mo96" wo="0.0010415835207694215" />
-        <nuclide name="Mo97" wo="0.0006048497176301975" />
-        <nuclide name="Mo98" wo="0.00154921076793649" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.506648724403529e-06" />
-        <nuclide name="B11" wo="2.449335127559647e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10005" name="Zircaloy-4">
-        <temperature>300</temperature>
-        <density units="g/cc" value="6.55" />
-        <nuclide name="O16" wo="0.0012494965182849112" />
-        <nuclide name="O17" wo="5.034817150887735e-07" />
-        <nuclide name="Cr50" wo="4.1736864731106146e-05" />
-        <nuclide name="Cr52" wo="0.0008369936242576807" />
-        <nuclide name="Cr53" wo="9.673586881507429e-05" />
-        <nuclide name="Cr54" wo="2.4533642196138756e-05" />
-        <nuclide name="Fe54" wo="0.00011855672274761877" />
-        <nuclide name="Fe56" wo="0.001929932104229657" />
-        <nuclide name="Fe57" wo="4.536774095388075e-05" />
-        <nuclide name="Fe58" wo="6.143432068843669e-06" />
-        <nuclide name="Zr90" wo="0.49750307249921255" />
-        <nuclide name="Zr91" wo="0.10970127796055709" />
-        <nuclide name="Zr92" wo="0.16952409354767467" />
-        <nuclide name="Zr94" wo="0.17553856942304608" />
-        <nuclide name="Zr96" wo="0.02888298656950975" />
-        <nuclide name="Sn112" wo="0.0001325869644430062" />
-        <nuclide name="Sn114" wo="9.182449637587617e-05" />
-        <nuclide name="Sn115" wo="4.771905922545867e-05" />
-        <nuclide name="Sn116" wo="0.002058423153629443" />
-        <nuclide name="Sn117" wo="0.0010966473429083066" />
-        <nuclide name="Sn118" wo="0.0034879812938438245" />
-        <nuclide name="Sn119" wo="0.001247577110245757" />
-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10006" name="Ag-In-Cd">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.16" />
-        <nuclide name="Ag107" wo="0.4110094082785408" />
-        <nuclide name="Ag109" wo="0.3889905917214592" />
-        <nuclide name="In113" wo="0.006314443289265887" />
-        <nuclide name="In115" wo="0.1436855567107341" />
-        <nuclide name="Cd106" wo="0.0005864650126662538" />
-        <nuclide name="Cd108" wo="0.0004261883300584398" />
-        <nuclide name="Cd110" wo="0.006095738560062021" />
-        <nuclide name="Cd111" wo="0.006311586256788057" />
-        <nuclide name="Cd112" wo="0.011999697873295025" />
-        <nuclide name="Cd113" wo="0.006140180186664414" />
-        <nuclide name="Cd114" wo="0.01456750341101345" />
-        <nuclide name="Cd116" wo="0.00387264036945234" />
-    </material>
-    <material id="10007" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032178659941803253" name="B10" />
-        <nuclide ao="0.0013017583017829388" name="B11" />
-        <nuclide ao="1.996441935899364" name="H1" />
-        <nuclide ao="0.0003109742982341739" name="H2" />
-        <nuclide ao="0.9979980704223166" name="O16" />
-        <nuclide ao="0.0003783846764824448" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10008" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.012259454378427138" name="B10" />
-        <nuclide ao="0.06018253698401973" name="B11" />
-        <nuclide ao="0.6509787013744828" name="O16" />
-        <nuclide ao="0.00024681447050525047" name="O17" />
-        <nuclide ao="0.23640592474731761" name="Si28" />
-        <nuclide ao="0.01200401834354893" name="Si29" />
-        <nuclide ao="0.007913102535354443" name="Si30" />
-        <nuclide ao="0.024236195272461444" name="Al27" />
-    </material>
-    <material id="10009" name="1.6% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.999242" name="O16" />
-        <nuclide ao="0.000758" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10010" name="2.4% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.999242" name="O16" />
-        <nuclide ao="0.000758" name="O17" />
-        <nuclide ao="0.000195223271243839" name="U234" />
-        <nuclide ao="0.024298776982208982" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10011" name="3.1% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.999242" name="O16" />
-        <nuclide ao="0.000758" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-</materials>

smr/fresh/plots.xml

@@ -1,79 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<plots>
-    <!--radial slice -->
-    <plot basis="xy" color="mat" filename="radial_xy_slice" id="10000" type="slice">
-        <origin>0.0 0.0 136.282</origin>
-        <width>268.7955 268.7955</width>
-        <pixels>1000 1000</pixels>
-        <background>255 255 255</background>
-        <col_spec id="10000" rgb="255 218 185" />
-        <col_spec id="10001" rgb="255 255 255" />
-        <col_spec id="10002" rgb="101 101 101" />
-        <col_spec id="10003" rgb="0 0 0" />
-        <col_spec id="10004" rgb="0 0 0" />
-        <col_spec id="10005" rgb="201 201 201" />
-        <col_spec id="10006" rgb="255 0 0" />
-        <col_spec id="10007" rgb="198 226 255" />
-        <col_spec id="10008" rgb="0 255 0" />
-        <col_spec id="10009" rgb="142 35 35" />
-        <col_spec id="10010" rgb="255 215 0" />
-        <col_spec id="10011" rgb="0 0 128" />
-    </plot>
-    <!--axial slice-->
-    <plot basis="xz" color="mat" filename="axial_xz_slice" id="10001" type="slice">
-        <origin>0.0 0.0 136.282</origin>
-        <width>270.0 272.564</width>
-        <pixels>1000 1000</pixels>
-        <background>255 255 255</background>
-        <col_spec id="10000" rgb="255 218 185" />
-        <col_spec id="10001" rgb="255 255 255" />
-        <col_spec id="10002" rgb="101 101 101" />
-        <col_spec id="10003" rgb="0 0 0" />
-        <col_spec id="10004" rgb="0 0 0" />
-        <col_spec id="10005" rgb="201 201 201" />
-        <col_spec id="10006" rgb="255 0 0" />
-        <col_spec id="10007" rgb="198 226 255" />
-        <col_spec id="10008" rgb="0 255 0" />
-        <col_spec id="10009" rgb="142 35 35" />
-        <col_spec id="10010" rgb="255 215 0" />
-        <col_spec id="10011" rgb="0 0 128" />
-    </plot>
-    <!--assembly grid spacer-->
-    <plot basis="xy" color="mat" filename="assm_grid_spacer" id="10002" type="slice">
-        <origin>0.0 0.0 102.021</origin>
-        <width>32.25546 32.25546</width>
-        <pixels>2000 2000</pixels>
-        <background>255 255 255</background>
-        <col_spec id="10000" rgb="255 218 185" />
-        <col_spec id="10001" rgb="255 255 255" />
-        <col_spec id="10002" rgb="101 101 101" />
-        <col_spec id="10003" rgb="0 0 0" />
-        <col_spec id="10004" rgb="0 0 0" />
-        <col_spec id="10005" rgb="201 201 201" />
-        <col_spec id="10006" rgb="255 0 0" />
-        <col_spec id="10007" rgb="198 226 255" />
-        <col_spec id="10008" rgb="0 255 0" />
-        <col_spec id="10009" rgb="142 35 35" />
-        <col_spec id="10010" rgb="255 215 0" />
-        <col_spec id="10011" rgb="0 0 128" />
-    </plot>
-    <!--assembly no spacer-->
-    <plot basis="xy" color="mat" filename="assm_no_spacer" id="10003" type="slice">
-        <origin>0.0 0.0 90.0</origin>
-        <width>32.25546 32.25546</width>
-        <pixels>2000 2000</pixels>
-        <background>255 255 255</background>
-        <col_spec id="10000" rgb="255 218 185" />
-        <col_spec id="10001" rgb="255 255 255" />
-        <col_spec id="10002" rgb="101 101 101" />
-        <col_spec id="10003" rgb="0 0 0" />
-        <col_spec id="10004" rgb="0 0 0" />
-        <col_spec id="10005" rgb="201 201 201" />
-        <col_spec id="10006" rgb="255 0 0" />
-        <col_spec id="10007" rgb="198 226 255" />
-        <col_spec id="10008" rgb="0 255 0" />
-        <col_spec id="10009" rgb="142 35 35" />
-        <col_spec id="10010" rgb="255 215 0" />
-        <col_spec id="10011" rgb="0 0 128" />
-    </plot>
-</plots>

smr/fresh/setting.xml

@@ -1,18 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<settings>
-    <eigenvalue>
-        <particles>10000</particles>
-        <batches>200</batches>
-        <inactive>100</inactive>
-    </eigenvalue>
-    <source strength="1.0">
-        <space type="fission">
-            <parameters>-75.26274000000001 -75.26274000000001 36.007 75.26274000000001 75.26274000000001 236.007</parameters>
-        </space>
-    </source>
-    <output>
-        <tallies>false</tallies>
-    </output>
-    <temperature_multipole>True</temperature_multipole>
-    <temperature_tolerance>1000</temperature_tolerance>
-</settings>

smr/fresh/tallies.xml

@@ -1,607 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<tallies>
-    <!--assembly mesh-->
-    <mesh id="10000" type="regular">
-        <dimension>119 119 100</dimension>
-        <lower_left>-75.26274000000001 -75.26274000000001 36.007</lower_left>
-        <width>1.26492 1.26492 200.0</width>
-    </mesh>
-    <tally id="10000" name="fission rates">
-        <filter bins="10000" type="mesh" />
-        <scores>fission</scores>
-    </tally>
-    <tally id="10001" name="u-238 capture">
-        <filter bins="10000" type="mesh" />
-        <nuclides>U238</nuclides>
-        <scores>absorption fission</scores>
-    </tally>
-    <tally id="10006">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10007">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10008">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10009">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10010">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10011">
-        <filter bins="10683" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10016">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10017">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10018">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10019">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10020">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10021">
-        <filter bins="10687" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10026">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10027">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10028">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10029">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10030">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10031">
-        <filter bins="10692" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10036">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10037">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10038">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10039">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10040">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10041">
-        <filter bins="10718" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10046">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10047">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10048">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10049">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10050">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10051">
-        <filter bins="10722" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10056">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10057">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10058">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10059">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10060">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10061">
-        <filter bins="10727" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10066">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10067">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10068">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10069">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10070">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10071">
-        <filter bins="10753" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10076">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10077">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10078">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10079">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10080">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10081">
-        <filter bins="10757" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10086">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10087">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10088">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10089">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10090">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10091">
-        <filter bins="10762" type="distribcell" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10246">
-        <filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10172">
-        <filter bins="10000 10001 10002 10006" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>He3 He4 O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 Ag107 Ag109 In113 In115 Cd106 Cd108 Cd110 Cd111 Cd112 Cd113 Cd114 Cd116</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10250">
-        <filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>total</nuclides>
-        <scores>flux</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10180">
-        <filter bins="10000 10001 10002 10006" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>He3 He4 O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 Ag107 Ag109 In113 In115 Cd106 Cd108 Cd110 Cd111 Cd112 Cd113 Cd114 Cd116</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10183">
-        <filter bins="10000 10001 10002 10006" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>He3 He4 O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 Ag107 Ag109 In113 In115 Cd106 Cd108 Cd110 Cd111 Cd112 Cd113 Cd114 Cd116</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10184">
-        <filter bins="10000 10001 10002 10006" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>He3 He4 O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 Ag107 Ag109 In113 In115 Cd106 Cd108 Cd110 Cd111 Cd112 Cd113 Cd114 Cd116</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10176">
-        <filter bins="10001 10002 10006" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 Ag107 Ag109 In113 In115 Cd106 Cd108 Cd110 Cd111 Cd112 Cd113 Cd114 Cd116</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10188">
-        <filter bins="10003 10007" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10195">
-        <filter bins="10003 10007" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10198">
-        <filter bins="10003 10007" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10199">
-        <filter bins="10003 10007" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10215">
-        <filter bins="10004 10009" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>C0 Mn55 P31 S32 S33 S34 S36 Si28 Si29 Si30 Ni58 Ni60 Ni61 Ni62 Ni64 Cr50 Cr52 Cr53 Cr54 Mo100 Mo92 Mo94 Mo95 Mo96 Mo97 Mo98 V50 V51 Nb93 Cu63 Cu65 Ca40 Ca42 Ca43 Ca44 Ca46 Ca48 B10 B11 Ti46 Ti47 Ti48 Ti49 Ti50 Al27 Fe54 Fe56 Fe57 Fe58 O16 O17 U234 U235 U238</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10222">
-        <filter bins="10004 10009" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>C0 Mn55 P31 S32 S33 S34 S36 Si28 Si29 Si30 Ni58 Ni60 Ni61 Ni62 Ni64 Cr50 Cr52 Cr53 Cr54 Mo100 Mo92 Mo94 Mo95 Mo96 Mo97 Mo98 V50 V51 Nb93 Cu63 Cu65 Ca40 Ca42 Ca43 Ca44 Ca46 Ca48 B10 B11 Ti46 Ti47 Ti48 Ti49 Ti50 Al27 Fe54 Fe56 Fe57 Fe58 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10225">
-        <filter bins="10004 10009" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>C0 Mn55 P31 S32 S33 S34 S36 Si28 Si29 Si30 Ni58 Ni60 Ni61 Ni62 Ni64 Cr50 Cr52 Cr53 Cr54 Mo100 Mo92 Mo94 Mo95 Mo96 Mo97 Mo98 V50 V51 Nb93 Cu63 Cu65 Ca40 Ca42 Ca43 Ca44 Ca46 Ca48 B10 B11 Ti46 Ti47 Ti48 Ti49 Ti50 Al27 Fe54 Fe56 Fe57 Fe58 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10226">
-        <filter bins="10004 10009" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>C0 Mn55 P31 S32 S33 S34 S36 Si28 Si29 Si30 Ni58 Ni60 Ni61 Ni62 Ni64 Cr50 Cr52 Cr53 Cr54 Mo100 Mo92 Mo94 Mo95 Mo96 Mo97 Mo98 V50 V51 Nb93 Cu63 Cu65 Ca40 Ca42 Ca43 Ca44 Ca46 Ca48 B10 B11 Ti46 Ti47 Ti48 Ti49 Ti50 Al27 Fe54 Fe56 Fe57 Fe58 O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10163">
-        <filter bins="10005" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10165">
-        <filter bins="10005" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10167">
-        <filter bins="10005" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10168">
-        <filter bins="10005" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 Cr50 Cr52 Cr53 Cr54 Fe54 Fe56 Fe57 Fe58 Zr90 Zr91 Zr92 Zr94 Zr96 Sn112 Sn114 Sn115 Sn116 Sn117 Sn118 Sn119 Sn120 Sn122 Sn124</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10190">
-        <filter bins="10007" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>B10 B11 H1 H2 O16 O17</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10206">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>total nu-fission</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10208">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10210">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10211">
-        <filter bins="10008" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>B10 B11 O16 O17 Si28 Si29 Si30 Al27</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10247">
-        <filter bins="10009 10010 10011" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission total</scores>
-        <estimator>tracklength</estimator>
-    </tally>
-    <tally id="10251">
-        <filter bins="10010 10011" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-scatter-P0</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10254">
-        <filter bins="10010 10011" type="material" />
-        <filter bins="0.0 20.0" type="energy" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-    <tally id="10255">
-        <filter bins="10010 10011" type="material" />
-        <filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
-        <nuclides>O16 O17 U234 U235 U238</nuclides>
-        <scores>nu-fission</scores>
-        <estimator>analog</estimator>
-    </tally>
-</tallies>

smr/geometry.xml

@@ -1,780 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<geometry>
-    <cell id="10000" material="10007" name="water pin" universe="10000" />
-    <cell id="10001" material="10007" name="GT empty (0)" region="-10004" universe="10001" />
-    <cell id="10002" material="10005" name="GT empty (1)" region="10004 -10005" universe="10001" />
-    <cell id="10003" material="10007" name="GT empty (last)" region="10005" universe="10001" />
-    <cell id="10004" material="10007" name="GT empty grid (bottom) (0)" region="-10004" universe="10002" />
-    <cell id="10005" material="10005" name="GT empty grid (bottom) (1)" region="10004 -10005" universe="10002" />
-    <cell id="10006" material="10007" name="GT empty grid (bottom) (last)" region="10005 10019 -10020 10021 -10022" universe="10002" />
-    <cell id="10007" material="10005" name="GT empty grid (bottom) (grid)" region="~(10019 -10020 10021 -10022)" universe="10002" />
-    <cell id="10008" material="10007" name="GT empty grid (intermediate) (0)" region="-10004" universe="10003" />
-    <cell id="10009" material="10005" name="GT empty grid (intermediate) (1)" region="10004 -10005" universe="10003" />
-    <cell id="10010" material="10007" name="GT empty grid (intermediate) (last)" region="10005 10019 -10020 10021 -10022" universe="10003" />
-    <cell id="10011" material="10005" name="GT empty grid (intermediate) (grid)" region="~(10019 -10020 10021 -10022)" universe="10003" />
-    <cell id="10012" material="10007" name="GT empty nozzle (0)" region="-10004" universe="10004" />
-    <cell id="10013" material="10005" name="GT empty nozzle (1)" region="10004 -10005" universe="10004" />
-    <cell id="10014" material="10007" name="GT empty nozzle (last)" region="10005" universe="10004" />
-    <cell id="10015" material="10007" name="GT empty at dashpot (0)" region="-10006" universe="10005" />
-    <cell id="10016" material="10005" name="GT empty at dashpot (1)" region="10006 -10007" universe="10005" />
-    <cell id="10017" material="10007" name="GT empty at dashpot (last)" region="10007" universe="10005" />
-    <cell id="10018" material="10007" name="GT empty at dashpot grid (bottom) (0)" region="-10006" universe="10006" />
-    <cell id="10019" material="10005" name="GT empty at dashpot grid (bottom) (1)" region="10006 -10007" universe="10006" />
-    <cell id="10020" material="10007" name="GT empty at dashpot grid (bottom) (last)" region="10007 10019 -10020 10021 -10022" universe="10006" />
-    <cell id="10021" material="10005" name="GT empty at dashpot grid (bottom) (grid)" region="~(10019 -10020 10021 -10022)" universe="10006" />
-    <cell id="10022" material="10007" name="GT empty at dashpot grid (intermediate) (0)" region="-10006" universe="10007" />
-    <cell id="10023" material="10005" name="GT empty at dashpot grid (intermediate) (1)" region="10006 -10007" universe="10007" />
-    <cell id="10024" material="10007" name="GT empty at dashpot grid (intermediate) (last)" region="10007 10019 -10020 10021 -10022" universe="10007" />
-    <cell id="10025" material="10005" name="GT empty at dashpot grid (intermediate) (grid)" region="~(10019 -10020 10021 -10022)" universe="10007" />
-    <cell id="10026" material="10007" name="GT empty nozzle (0)" region="-10006" universe="10008" />
-    <cell id="10027" material="10005" name="GT empty nozzle (1)" region="10006 -10007" universe="10008" />
-    <cell id="10028" material="10007" name="GT empty nozzle (last)" region="10007" universe="10008" />
-    <cell fill="10000" id="10029" name="GT empty (0)" region="-10031" universe="10009" />
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-    <cell fill="10000" id="10031" name="GT empty (2)" region="10032 -10033" universe="10009" />
-    <cell fill="10005" id="10032" name="GT empty (3)" region="10033 -10034" universe="10009" />
-    <cell fill="10005" id="10033" name="GT empty (4)" region="10034 -10037" universe="10009" />
-    <cell fill="10006" id="10034" name="GT empty (5)" region="10037 -10038" universe="10009" />
-    <cell fill="10005" id="10035" name="GT empty (6)" region="10038 -10039" universe="10009" />
-    <cell fill="10001" id="10036" name="GT empty (7)" region="10039 -10040" universe="10009" />
-    <cell fill="10003" id="10037" name="GT empty (8)" region="10040 -10041" universe="10009" />
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-    <cell fill="10000" id="10050" name="GT empty instr (0)" region="-10031" universe="10010" />
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-    <cell id="10072" material="10005" name="IT (1)" region="10015 -10016" universe="10011" />
-    <cell id="10073" material="10007" name="IT (2)" region="10016 -10004" universe="10011" />
-    <cell id="10074" material="10005" name="IT (3)" region="10004 -10005" universe="10011" />
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-    <cell id="10076" material="10001" name="IT grid (bottom) (0)" region="-10015" universe="10012" />
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-    <surface coeffs="0.0 0.0 85.0" id="10070" name="core barrel IR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 90.0" id="10071" name="core barrel OR" type="z-cylinder" />
-    <surface coeffs="0.0 0.0 92.0" id="10072" name="neutron shield OR" type="z-cylinder" />
-    <surface coeffs="1.0 1.7320508075688767 0.0 0.0" id="10073" name="neutron shield NWbot SEtop" type="plane" />
-    <surface coeffs="1.0 0.5773502691896257 0.0 0.0" id="10074" name="neutron shield NWtop SEbot" type="plane" />
-    <surface coeffs="1.0 -1.7320508075688767 0.0 0.0" id="10075" name="neutron shield NEbot SWtop" type="plane" />
-    <surface coeffs="1.0 -0.5773502691896257 0.0 0.0" id="10076" name="neutron shield NEtop SWbot" type="plane" />
-    <surface coeffs="0.0 0.0 120.0" id="10077" name="RPV IR" type="z-cylinder" />
-    <surface boundary="vacuum" coeffs="0.0 0.0 135.0" id="10078" name="RPV OR" type="z-cylinder" />
-    <surface boundary="vacuum" coeffs="272.564" id="10079" name="upper problem boundary" type="z-plane" />
-    <surface boundary="vacuum" coeffs="0.0" id="10080" name="lower problem boundary" type="z-plane" />
-    <surface coeffs="3.15341" id="10081" name="baffle north" type="y-plane" />
-    <surface coeffs="-3.15341" id="10082" name="baffle south" type="y-plane" />
-    <surface coeffs="3.15341" id="10083" name="baffle east" type="x-plane" />
-    <surface coeffs="-3.15341" id="10084" name="baffle west" type="x-plane" />
-</geometry>

smr/materials.xml

@@ -1,211 +0,0 @@
-<?xml version='1.0' encoding='utf-8'?>
-<materials>
-    <material id="10000" name="Helium">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.0015981" />
-        <nuclide ao="1.34e-06" name="He3" />
-        <nuclide ao="0.99999866" name="He4" />
-    </material>
-    <material id="10001" name="Air">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.00616" />
-        <nuclide ao="0.20942038999999998" name="O16" />
-        <nuclide ao="7.961e-05" name="O17" />
-        <nuclide ao="0.7780575240000001" name="N14" />
-        <nuclide ao="0.002842476" name="N15" />
-        <nuclide ao="3.1124879999999996e-05" name="Ar36" />
-        <nuclide ao="5.86857e-06" name="Ar38" />
-        <nuclide ao="0.00929300655" name="Ar40" />
-        <nuclide ao="0.00027" name="C0" />
-    </material>
-    <material id="10002" name="Inconel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.2" />
-        <nuclide name="Si28" wo="0.003215327037608538" />
-        <nuclide name="Si29" wo="0.0001691770106155053" />
-        <nuclide name="Si30" wo="0.00011549595177595707" />
-        <nuclide name="Cr50" wo="0.007913309553017726" />
-        <nuclide name="Cr52" wo="0.15869399115925625" />
-        <nuclide name="Cr53" wo="0.018341120727338085" />
-        <nuclide name="Cr54" wo="0.004651578560387908" />
-        <nuclide name="Mn55" wo="0.0087" />
-        <nuclide name="Fe54" wo="0.016163233201258693" />
-        <nuclide name="Fe56" wo="0.26311407687664323" />
-        <nuclide name="Fe57" wo="0.006185135350045743" />
-        <nuclide name="Fe58" wo="0.0008375545720523535" />
-        <nuclide name="Ni58" wo="0.3439855822298418" />
-        <nuclide name="Ni60" wo="0.13706564068516966" />
-        <nuclide name="Ni61" wo="0.006057615566737856" />
-        <nuclide name="Ni62" wo="0.01963099676371214" />
-        <nuclide name="Ni64" wo="0.0051601647545385385" />
-    </material>
-    <material id="10003" name="SS304">
-        <temperature>300</temperature>
-        <density units="g/cc" value="8.03" />
-        <nuclide name="Si28" wo="0.0055119892073289215" />
-        <nuclide name="Si29" wo="0.0002900177324837234" />
-        <nuclide name="Si30" wo="0.00019799306018735498" />
-        <nuclide name="Cr50" wo="0.007930004298910168" />
-        <nuclide name="Cr52" wo="0.15902878860895933" />
-        <nuclide name="Cr53" wo="0.018379815074864116" />
-        <nuclide name="Cr54" wo="0.004661392017266364" />
-        <nuclide name="Mn55" wo="0.02" />
-        <nuclide name="Fe54" wo="0.03861561826636726" />
-        <nuclide name="Fe56" wo="0.6286064568062312" />
-        <nuclide name="Fe57" wo="0.014776921339264018" />
-        <nuclide name="Fe58" wo="0.002001003588137652" />
-        <nuclide name="Ni58" wo="0.06719780860125842" />
-        <nuclide name="Ni60" wo="0.026775862606987628" />
-        <nuclide name="Ni61" wo="0.0011833591652154437" />
-        <nuclide name="Ni62" wo="0.0038349280648001835" />
-        <nuclide name="Ni64" wo="0.0010080415617383354" />
-    </material>
-    <material id="10004" name="Carbon Steel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="7.8" />
-        <nuclide name="C0" wo="0.0027" />
-        <nuclide name="Mn55" wo="0.0075" />
-        <nuclide name="P31" wo="0.00025" />
-        <nuclide name="S32" wo="0.00023678833437985024" />
-        <nuclide name="S33" wo="1.928017942950141e-06" />
-        <nuclide name="S34" wo="1.1255605170437904e-05" />
-        <nuclide name="S36" wo="2.8042506761729612e-08" />
-        <nuclide name="Si28" wo="0.0036746594715526145" />
-        <nuclide name="Si29" wo="0.00019334515498914892" />
-        <nuclide name="Si30" wo="0.00013199537345823665" />
-        <nuclide name="Ni58" wo="0.005039835645094381" />
-        <nuclide name="Ni60" wo="0.002008189695524072" />
-        <nuclide name="Ni61" wo="8.875193739115826e-05" />
-        <nuclide name="Ni62" wo="0.0002876196048600137" />
-        <nuclide name="Ni64" wo="7.560311713037514e-05" />
-        <nuclide name="Cr50" wo="0.00014607902655887153" />
-        <nuclide name="Cr52" wo="0.0029294776849018824" />
-        <nuclide name="Cr53" wo="0.00033857554085276" />
-        <nuclide name="Cr54" wo="8.586774768648565e-05" />
-        <nuclide name="Mo100" wo="0.0006389990196986576" />
-        <nuclide name="Mo92" wo="0.0008697692153084613" />
-        <nuclide name="Mo94" wo="0.0005596299371553791" />
-        <nuclide name="Mo95" wo="0.0009791265884380354" />
-        <nuclide name="Mo96" wo="0.0010412766216951505" />
-        <nuclide name="Mo97" wo="0.0006059164130800636" />
-        <nuclide name="Mo98" wo="0.0015552822046242536" />
-        <nuclide name="V50" wo="1.2256016778573164e-06" />
-        <nuclide name="V51" wo="0.0004987743983221427" />
-        <nuclide name="Nb93" wo="0.0001" />
-        <nuclide name="Cu63" wo="0.001369583906732317" />
-        <nuclide name="Cu65" wo="0.0006304160932676829" />
-        <nuclide name="Ca40" wo="0.00014499268968855714" />
-        <nuclide name="Ca42" wo="1.0160391170196e-06" />
-        <nuclide name="Ca43" wo="2.1705537495761849e-07" />
-        <nuclide name="Ca44" wo="3.4317237524995553e-06" />
-        <nuclide name="Ca46" wo="6.8796341950755285e-09" />
-        <nuclide name="Ca48" wo="3.3561243277098485e-07" />
-        <nuclide name="B10" wo="5.529283001779395e-06" />
-        <nuclide name="B11" wo="2.4470716998220607e-05" />
-        <nuclide name="Ti46" wo="1.1880142852196743e-05" />
-        <nuclide name="Ti47" wo="1.0946673488791549e-05" />
-        <nuclide name="Ti48" wo="0.00011076757837453494" />
-        <nuclide name="Ti49" wo="8.298285799079257e-06" />
-        <nuclide name="Ti50" wo="8.107319485397494e-06" />
-        <nuclide name="Al27" wo="0.00025" />
-        <nuclide name="Fe54" wo="0.054472297655949964" />
-        <nuclide name="Fe56" wo="0.8867302806705092" />
-        <nuclide name="Fe57" wo="0.020844748673414723" />
-        <nuclide name="Fe58" wo="0.0028226730001262813" />
-    </material>
-    <material id="10005" name="Zircaloy-4">
-        <temperature>300</temperature>
-        <density units="g/cc" value="6.55" />
-        <nuclide name="O16" wo="0.001249495189868807" />
-        <nuclide name="O17" wo="5.048101311928357e-07" />
-        <nuclide name="Cr50" wo="4.1736864731106146e-05" />
-        <nuclide name="Cr52" wo="0.0008369936242576807" />
-        <nuclide name="Cr53" wo="9.673586881507429e-05" />
-        <nuclide name="Cr54" wo="2.4533642196138756e-05" />
-        <nuclide name="Fe54" wo="0.00011855672274761877" />
-        <nuclide name="Fe56" wo="0.001929932104229657" />
-        <nuclide name="Fe57" wo="4.536774095388075e-05" />
-        <nuclide name="Fe58" wo="6.143432068843669e-06" />
-        <nuclide name="Zr90" wo="0.49750307249921255" />
-        <nuclide name="Zr91" wo="0.10970127796055709" />
-        <nuclide name="Zr92" wo="0.16952409354767467" />
-        <nuclide name="Zr94" wo="0.17553856942304608" />
-        <nuclide name="Zr96" wo="0.02888298656950975" />
-        <nuclide name="Sn112" wo="0.0001325869644430062" />
-        <nuclide name="Sn114" wo="9.182449637587617e-05" />
-        <nuclide name="Sn115" wo="4.771905922545867e-05" />
-        <nuclide name="Sn116" wo="0.002058423153629443" />
-        <nuclide name="Sn117" wo="0.0010966473429083066" />
-        <nuclide name="Sn118" wo="0.0034879812938438245" />
-        <nuclide name="Sn119" wo="0.001247577110245757" />
-        <nuclide name="Sn120" wo="0.004771539495238715" />
-        <nuclide name="Sn122" wo="0.0006894094798456136" />
-        <nuclide name="Sn124" wo="0.000876291604244001" />
-    </material>
-    <material id="10006" name="Ag-In-Cd">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.16" />
-        <nuclide name="Ag107" wo="0.4110094082785408" />
-        <nuclide name="Ag109" wo="0.3889905917214592" />
-        <nuclide name="In113" wo="0.006327728141638555" />
-        <nuclide name="In115" wo="0.14367227185836143" />
-        <nuclide name="Cd106" wo="0.0005888321338146614" />
-        <nuclide name="Cd108" wo="0.0004271568027625324" />
-        <nuclide name="Cd110" wo="0.006105637975143767" />
-        <nuclide name="Cd111" wo="0.006314179646316293" />
-        <nuclide name="Cd112" wo="0.012010391637811244" />
-        <nuclide name="Cd113" wo="0.0061367883079578595" />
-        <nuclide name="Cd114" wo="0.01455563708243845" />
-        <nuclide name="Cd116" wo="0.003861376413755194" />
-    </material>
-    <material id="10007" name="Borated Water">
-        <temperature>300</temperature>
-        <density units="g/cc" value="0.7405820675158279" />
-        <nuclide ao="0.00032310954757148997" name="B10" />
-        <nuclide ao="0.001300556520626952" name="B11" />
-        <nuclide ao="1.9965230413067991" name="H1" />
-        <nuclide ao="0.0002296265568043144" name="H2" />
-        <nuclide ao="0.9979969509249076" name="O16" />
-        <nuclide ao="0.00037938300689408465" name="O17" />
-        <sab name="c_H_in_H2O" />
-    </material>
-    <material id="10008" name="Borosilicate Glass">
-        <temperature>300</temperature>
-        <density units="g/cc" value="2.26" />
-        <nuclide ao="0.01225951735682195" name="B10" />
-        <nuclide ao="0.06018284614945709" name="B11" />
-        <nuclide ao="0.6509773086458921" name="O16" />
-        <nuclide ao="0.0002474654141428133" name="O17" />
-        <nuclide ao="0.23638904846495962" name="Si28" />
-        <nuclide ao="0.01200874718951168" name="Si29" />
-        <nuclide ao="0.007925516821765233" name="Si30" />
-        <nuclide ao="0.02423631977691551" name="Al27" />
-    </material>
-    <material id="10009" name="1.6% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.31341" />
-        <nuclide ao="1.99924" name="O16" />
-        <nuclide ao="0.00076" name="O17" />
-        <nuclide ao="0.00013098435147670763" name="U234" />
-        <nuclide ao="0.01630317699531038" name="U235" />
-        <nuclide ao="0.9835658386532129" name="U238" />
-    </material>
-    <material id="10010" name="2.4% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.29748" />
-        <nuclide ao="1.99924" name="O16" />
-        <nuclide ao="0.00076" name="O17" />
-        <nuclide ao="0.000195223271243839" name="U234" />
-        <nuclide ao="0.024298776982208982" name="U235" />
-        <nuclide ao="0.9755059997465472" name="U238" />
-    </material>
-    <material id="10011" name="3.1% Enr. UO2 Fuel">
-        <temperature>300</temperature>
-        <density units="g/cc" value="10.30166" />
-        <nuclide ao="1.99924" name="O16" />
-        <nuclide ao="0.00076" name="O17" />
-        <nuclide ao="0.0002523276152188021" name="U234" />
-        <nuclide ao="0.03140636057161555" name="U235" />
-        <nuclide ao="0.9683413118131656" name="U238" />
-    </material>
-</materials>

smr/milestones.md

@@ -0,0 +1,20 @@
+# Milestone Models
+
+- **AD-SE-08-61, Coupled Multiphysics Driver Implementation** --- This milestone
+  used the singlerod short/long problems. Generating the model was done with the
+  script `tests/singlerod/make_openmc_model.py` from the ENRICO repository
+  (there is a `--short` command line option to generate the short version)
+
+- **AD-SE-08-66, Coupled Assembly Analysis** --- This milestone used the
+  assembly short and long (v2) problems. Generating the model was done with
+  `smr/build-assembly-long.py -a 100 --clone` on the ecp-benchmarks repository
+  (git commit `631fefe`, after pull request #14). In these models, materials are
+  fully differentiated across each fuel ring/axial segment.
+
+- **AD-SE-08-73, Full core coupled-physics simulation** --- This milestone used
+  the core-short and core-long (90 layer) models. Generating the models was done
+  with `smr/build-core-short.py` and `smr/build-assembly-long.py -a 90` on the
+  ecp-benchmarks repository (git commit `c7b89db`, after pull request #16). In
+  these models, materials are not differentiated and no grid spacers are
+  present. The lattice pitch is modified to be exactly 17 times the pin pitch
+  (slightly different than NuScale specification).