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Added distribmat and depletion tallies to 2x2 benchmarks

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This commit is contained in:
Will Boyd 2017-04-09 15:27:48 -04:00
parent 1cba3041ba
commit d46e63dbbe
11 changed files with 174 additions and 1059 deletions
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146
2x2-periodic/build-fresh.py
View file

@ -2,6 +2,7 @@
import os
import shutil
import copy
import numpy as np
import openmc
@ -9,8 +10,54 @@ import openmc
from geometry import beavrs, openmc_geometry
#### Query the user for options
# Query the user on whether to use multipole cross sections
multipole = input('Use multipole cross sections? (y/n): ').lower()
multipole = (multipole == 'y')
# Query the user on whether to use distribmats or distribcells
# If using distribmats, the geometry must be "differentiated" with unique
# material instances for each instance of a fuel cell
distrib = input('Use distribmat or distribcells? [mat/cell]: ').lower()
if distrib not in ['cell', 'mat']:
raise InputError('Distrib type "{}" is unsupported'.format(distrib))
#### "Differentiate" the geometry if using distribmats
if distrib == 'mat':
# Count the number of instances for each cell and material
openmc_geometry.determine_paths()
# Determine the maximum material ID
max_material_id = 0
for material in openmc_geometry.get_all_materials().values():
max_material_id = max(max_material_id, material.id)
# Extract all cells filled by a fuel material
fuel_cells = openmc_geometry.get_cells_by_name(
name='enr radial 0: Fuel', case_sensitive=True)
# Assign distribmats for each material
for cell in fuel_cells:
new_materials = []
for i in range(cell.num_instances):
new_material = copy.deepcopy(cell.fill)
new_material.id = max_material_id + 1
max_material_id += 1
new_materials.append(new_material)
# Fill cell with list of "differentiated" materials
cell.fill = new_materials
#### Create OpenMC "materials.xml" file
beavrs.write_openmc_materials()
all_materials = openmc_geometry.get_all_materials()
materials = openmc.Materials(all_materials.values())
materials.export_to_xml()
#### Create OpenMC "geometry.xml" file
@ -19,10 +66,6 @@ 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 = (multipole == 'y')
# Construct uniform initial source distribution over fissionable zones
lower_left = [-21.41728, -21.41728, +192.5]
upper_right = [+21.41728, +21.41728, +197.5]
@ -54,80 +97,41 @@ plot.width = [21.41728*2, 21.41728*2]
plot.origin = [0., 0., 195.]
plot.color_by = 'material'
plot.filename = '2x2-periodic'
plot.colors = beavrs.plots.colors_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
fuel_cells = []
for cell in openmc_geometry.get_all_material_cells().values():
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 /= mesh.dimension
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
tallies = openmc.Tallies()
# 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()
# Extract all fuel materials
materials = openmc_geometry.get_materials_by_name(name='Fuel', matching=False)
# If using distribcells, create distribcell tally needed for depletion
if distrib == 'cell':
fuel_cells = openmc_geometry.get_cells_by_name(
name='enr radial 0: Fuel', case_sensitive=True, matching=False)
for cell in fuel_cells:
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.id]))
tallies.append(tally)
# If using distribmats, create material tally needed for depletion
elif distrib == '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()
material_ids = [material.id for material in materials]
tally.filters.append(openmc.MaterialFilter(material_ids))
tallies.append(tally)
tallies.export_to_xml()
#### Move all XML files to 'fresh' directory

103
2x2-periodic/fresh/materials.xml
View file

@ -33,29 +33,6 @@
<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" />
@ -112,59 +89,6 @@
<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" />
@ -174,15 +98,6 @@
<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" />
@ -192,24 +107,6 @@
<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" />

15
2x2-periodic/fresh/plots.xml
View file

@ -4,20 +4,5 @@
<origin>0.0 0.0 195.0</origin>
<width>42.83456 42.83456</width>
<pixels>1000 1000</pixels>
<color id="10013" rgb="0 255 0" />
<color id="10001" rgb="0 0 0" />
<color id="10006" rgb="111 111 111" />
<color id="10016" rgb="112 128 144" />
<color id="10007" rgb="50 50 50" />
<color id="10014" rgb="198 226 255" />
<color id="10003" rgb="200 50 50" />
<color id="10000" rgb="255 255 255" />
<color id="10008" rgb="142 35 35" />
<color id="10015" rgb="176 196 222" />
<color id="10002" rgb="255 0 0" />
<color id="10005" rgb="101 101 101" />
<color id="10010" rgb="0 0 128" />
<color id="10009" rgb="255 215 0" />
<color id="10004" rgb="255 218 185" />
</plot>
</plots>

330
2x2-periodic/fresh/tallies.xml
View file

@ -1,335 +1,13 @@
<?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">
<tally id="10000" name="depletion tally">
<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>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
</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-0</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="10016">
<tally id="10001" name="depletion tally">
<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>
</tally>
<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>
</tally>
<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>
</tally>
<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" />
<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-0</scores>
<estimator>analog</estimator>
</tally>
<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="10159">
<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>
</tally>
<tally id="10074">
<filter bins="10004 10014 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 He3 He4</nuclides>
<scores>total nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10163">
<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="10082">
<filter bins="10004 10014 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>B10 B11 H1 H2 O16 O17 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10085">
<filter bins="10004 10014 10016" type="material" />
<filter bins="0.0 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 He3 He4</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10086">
<filter bins="10004 10014 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>B10 B11 H1 H2 O16 O17 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="10078">
<filter bins="10004 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>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238 He3 He4</nuclides>
<scores>nu-fission total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<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="10055">
<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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<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="10058">
<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="10090">
<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>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="10097">
<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>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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10100">
<filter bins="10005 10008" 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="10101">
<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>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="10105">
<filter bins="10005 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" />
<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 total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10141">
<filter bins="10001 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" />
<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>nu-fission total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10149">
<filter bins="10001 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 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10152">
<filter bins="10001 10015" type="material" />
<filter bins="0.0 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>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10153">
<filter bins="10001 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 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="10145">
<filter bins="10000 10001" 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</nuclides>
<scores>total nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10122">
<filter bins="10000" 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</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10124">
<filter bins="10000" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10125">
<filter bins="10000" 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</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10132">
<filter bins="10010" 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="10134">
<filter bins="10010" 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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10136">
<filter bins="10010" 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="10137">
<filter bins="10010" 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="10160">
<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="10162">
<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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10164">
<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="10165">
<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>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
</tally>
</tallies>

146
2x2-reflector/build-fresh.py
View file

@ -2,6 +2,7 @@
import os
import shutil
import copy
import numpy as np
import openmc
@ -9,8 +10,54 @@ import openmc
from geometry import beavrs, openmc_geometry
#### Query the user for options
# Query the user on whether to use multipole cross sections
multipole = input('Use multipole cross sections? (y/n): ').lower()
multipole = (multipole == 'y')
# Query the user on whether to use distribmats or distribcells
# If using distribmats, the geometry must be "differentiated" with unique
# material instances for each instance of a fuel cell
distrib = input('Use distribmat or distribcells? [mat/cell]: ').lower()
if distrib not in ['cell', 'mat']:
raise InputError('Distrib type "{}" is unsupported'.format(distrib))
#### "Differentiate" the geometry if using distribmats
if distrib == 'mat':
# Count the number of instances for each cell and material
openmc_geometry.determine_paths()
# Determine the maximum material ID
max_material_id = 0
for material in openmc_geometry.get_all_materials().values():
max_material_id = max(max_material_id, material.id)
# Extract all cells filled by a fuel material
fuel_cells = openmc_geometry.get_cells_by_name(
name='enr radial 0: Fuel', case_sensitive=True)
# Assign distribmats for each material
for cell in fuel_cells:
new_materials = []
for i in range(cell.num_instances):
new_material = copy.deepcopy(cell.fill)
new_material.id = max_material_id + 1
max_material_id += 1
new_materials.append(new_material)
# Fill cell with list of "differentiated" materials
cell.fill = new_materials
#### Create OpenMC "materials.xml" file
beavrs.write_openmc_materials()
all_materials = openmc_geometry.get_all_materials()
materials = openmc.Materials(all_materials.values())
materials.export_to_xml()
#### Create OpenMC "geometry.xml" file
@ -19,10 +66,6 @@ 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 = (multipole == 'y')
# Construct uniform initial source distribution over fissionable zones
lower_left = [-32.12592, -32.12592, 192.5]
upper_right = [32.12592, 32.12592, 197.5]
@ -57,80 +100,41 @@ plot.width = [64.25184, 64.25184]
plot.origin = [0., 0., 195.]
plot.color_by = 'material'
plot.filename = '2x2-reflector'
plot.colors = beavrs.plots.colors_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
fuel_cells = []
for cell in openmc_geometry.get_all_material_cells().values():
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 /= mesh.dimension
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
tallies = openmc.Tallies()
# 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()
# Extract all fuel materials
materials = openmc_geometry.get_materials_by_name(name='Fuel', matching=False)
# If using distribcells, create distribcell tally needed for depletion
if distrib == 'cell':
fuel_cells = openmc_geometry.get_cells_by_name(
name='enr radial 0: Fuel', case_sensitive=True, matching=False)
for cell in fuel_cells:
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.id]))
tallies.append(tally)
# If using distribmats, create material tally needed for depletion
elif distrib == '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()
material_ids = [material.id for material in materials]
tally.filters.append(openmc.MaterialFilter(material_ids))
tallies.append(tally)
tallies.export_to_xml()
#### Move all XML files to 'fresh' directory

103
2x2-reflector/fresh/materials.xml
View file

@ -33,29 +33,6 @@
<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" />
@ -112,59 +89,6 @@
<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" />
@ -174,15 +98,6 @@
<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" />
@ -192,24 +107,6 @@
<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" />

15
2x2-reflector/fresh/plots.xml
View file

@ -4,20 +4,5 @@
<origin>0.0 0.0 195.0</origin>
<width>64.25184 64.25184</width>
<pixels>1000 1000</pixels>
<color id="10006" rgb="111 111 111" />
<color id="10004" rgb="255 218 185" />
<color id="10005" rgb="101 101 101" />
<color id="10013" rgb="0 255 0" />
<color id="10002" rgb="255 0 0" />
<color id="10015" rgb="176 196 222" />
<color id="10000" rgb="255 255 255" />
<color id="10014" rgb="198 226 255" />
<color id="10009" rgb="255 215 0" />
<color id="10016" rgb="112 128 144" />
<color id="10003" rgb="200 50 50" />
<color id="10007" rgb="50 50 50" />
<color id="10008" rgb="142 35 35" />
<color id="10010" rgb="0 0 128" />
<color id="10001" rgb="0 0 0" />
</plot>
</plots>

330
2x2-reflector/fresh/tallies.xml
View file

@ -1,335 +1,13 @@
<?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>0.62992 0.62992 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">
<tally id="10000" name="depletion tally">
<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>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
</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-0</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="10016">
<tally id="10001" name="depletion tally">
<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>
</tally>
<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>
</tally>
<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>
</tally>
<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" />
<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-0</scores>
<estimator>analog</estimator>
</tally>
<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="10159">
<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>
</tally>
<tally id="10074">
<filter bins="10004 10014 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 He3 He4</nuclides>
<scores>total nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10163">
<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="10082">
<filter bins="10004 10014 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>B10 B11 H1 H2 O16 O17 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 He3 He4</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10085">
<filter bins="10004 10014 10016" type="material" />
<filter bins="0.0 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 He3 He4</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10086">
<filter bins="10004 10014 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>B10 B11 H1 H2 O16 O17 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="10078">
<filter bins="10004 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>Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64 O16 O17 U234 U235 U238 He3 He4</nuclides>
<scores>nu-fission total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<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="10055">
<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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<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="10058">
<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="10090">
<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>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="10097">
<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>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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10100">
<filter bins="10005 10008" 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="10101">
<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>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="10105">
<filter bins="10005 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" />
<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 total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10141">
<filter bins="10001 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" />
<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>nu-fission total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10149">
<filter bins="10001 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 Si28 Si29 Si30 Cr50 Cr52 Cr53 Cr54 Mn55 Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Ni61 Ni62 Ni64</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10152">
<filter bins="10001 10015" type="material" />
<filter bins="0.0 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>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10153">
<filter bins="10001 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 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="10145">
<filter bins="10000 10001" 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</nuclides>
<scores>total nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10122">
<filter bins="10000" 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</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10124">
<filter bins="10000" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>O16 O17 N14 N15 Ar36 Ar38 Ar40 C0</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10125">
<filter bins="10000" 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</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10132">
<filter bins="10010" 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="10134">
<filter bins="10010" 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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10136">
<filter bins="10010" 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="10137">
<filter bins="10010" 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="10160">
<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="10162">
<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-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10164">
<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="10165">
<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>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
</tally>
</tallies>

28
assembly/build-fresh.py
View file

@ -97,7 +97,6 @@ plot.width = [10.70864*2, 10.70864*2]
plot.origin = [0., 0., 195.]
plot.color_by = 'material'
plot.filename = 'assembly'
plot.colors = beavrs.plots.colors_mat
plot.pixels = [1000, 1000]
plot_file = openmc.Plots([plot])
@ -105,30 +104,33 @@ plot_file.export_to_xml()
#### Create OpenMC "tallies.xml" file
tallies = openmc.Tallies()
# Extract all fuel materials
materials = openmc_geometry.get_materials_by_name(name='Fuel 1.6%')
# Create a single tally akin to that used by OpenDeplete
tally = openmc.Tally(name='depletion tally')
tally.scores = \
['(n,p)', '(n,a)', '(n,gamma)', 'fission', '(n,2n)', '(n,3n)', '(n,4)']
tally.nuclides = materials[0].get_nuclides()
materials = openmc_geometry.get_materials_by_name(name='Fuel', matching=False)
# If using distribcells, create distribcell tally needed for depletion
if distrib == 'cell':
if distrib == 'cell':
fuel_cells = openmc_geometry.get_cells_by_name(
name='enr radial 0: Fuel', case_sensitive=True)
tally.filters.append(openmc.DistribcellFilter([fuel_cells[0].id]))
name='enr radial 0: Fuel', case_sensitive=True, matching=False)
for cell in fuel_cells:
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.id]))
tallies.append(tally)
# If using distribmats, create material tally needed for depletion
elif distrib == '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()
material_ids = [material.id for material in materials]
tally.filters.append(openmc.MaterialFilter(material_ids))
tallies.append(tally)
tallies.append(tally)
tallies.export_to_xml()

15
assembly/fresh/plots.xml
View file

@ -4,20 +4,5 @@
<origin>0.0 0.0 195.0</origin>
<width>21.41728 21.41728</width>
<pixels>1000 1000</pixels>
<color id="10000" rgb="255 255 255" />
<color id="10001" rgb="0 0 0" />
<color id="10002" rgb="255 0 0" />
<color id="10003" rgb="200 50 50" />
<color id="10004" rgb="255 218 185" />
<color id="10005" rgb="101 101 101" />
<color id="10006" rgb="111 111 111" />
<color id="10007" rgb="50 50 50" />
<color id="10008" rgb="142 35 35" />
<color id="10009" rgb="255 215 0" />
<color id="10010" rgb="0 0 128" />
<color id="10013" rgb="0 255 0" />
<color id="10014" rgb="198 226 255" />
<color id="10015" rgb="176 196 222" />
<color id="10016" rgb="112 128 144" />
</plot>
</plots>

2
assembly/fresh/tallies.xml
View file

@ -3,6 +3,6 @@
<tally id="10000" name="depletion tally">
<filter bins="10053" type="distribcell" />
<nuclides>O16 O17 U234 U235 U238</nuclides>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4)</scores>
<scores>(n,p) (n,a) (n,gamma) fission (n,2n) (n,3n) (n,4n)</scores>
</tally>
</tallies>