mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 06:05:58 -04:00
Merge branch 'develop' of https://github.com/mit-crpg/openmc into new-update
updating openmc
This commit is contained in:
Jose Salcedo Perez
commit
d0e203c6e1
6 changed files with 244 additions and 64 deletions
|
|
@ -148,8 +148,8 @@ Prerequisites
|
|||
.. important::
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||||
|
||||
If you are building HDF5 version 1.8.x or earlier, you must include
|
||||
``--enable-fortran2003`` when configuring HDF5 or else OpenMC will not
|
||||
be able to compile.
|
||||
``--enable-fortran2003`` as well when configuring HDF5 or else OpenMC
|
||||
will not be able to compile.
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||||
|
||||
.. admonition:: Optional
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||||
:class: note
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||||
|
|
@ -416,7 +416,9 @@ Prerequisites
|
|||
The Python API works with Python 3.4+. In addition to Python itself, the API
|
||||
relies on a number of third-party packages. All prerequisites can be installed
|
||||
using Conda_ (recommended), pip_, or through the package manager in most Linux
|
||||
distributions.
|
||||
distributions. To run simulations in parallel using MPI, it is recommended to
|
||||
build mpi4py, HDF5, h5py from source, in that order, using the same compilers
|
||||
as for OpenMC.
|
||||
|
||||
.. admonition:: Required
|
||||
:class: error
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||||
|
|
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|||
|
|
@ -261,7 +261,7 @@ The following tables show all valid scores:
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|||
+----------------------+---------------------------------------------------+
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|Score | Description |
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||||
+======================+===================================================+
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|current |Used in combination with a mesh filter: |
|
||||
|current |Used in combination with a meshsurface filter: |
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||||
| |Partial currents on the boundaries of each cell in |
|
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| |a mesh. It may not be used in conjunction with any |
|
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| |other score. Only energy and mesh filters may be |
|
||||
|
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@ -269,7 +269,7 @@ The following tables show all valid scores:
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|||
| |Used in combination with a surface filter: |
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| |Net currents on any surface previously defined in |
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||||
| |the geometry. It may be used along with any other |
|
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| |filter, except mesh filters. |
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| |filter, except meshsurface filters. |
|
||||
| |Surfaces can alternatively be defined with cell |
|
||||
| |from and cell filters thereby resulting in tallying|
|
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| |partial currents. |
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|
|
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|
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@ -287,18 +287,7 @@
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|||
"metadata": {
|
||||
"collapsed": false
|
||||
},
|
||||
"outputs": [
|
||||
{
|
||||
"data": {
|
||||
"text/plain": [
|
||||
"0"
|
||||
]
|
||||
},
|
||||
"execution_count": 11,
|
||||
"metadata": {},
|
||||
"output_type": "execute_result"
|
||||
}
|
||||
],
|
||||
"outputs": [],
|
||||
"source": [
|
||||
"# Run openmc in plotting mode\n",
|
||||
"openmc.plot_geometry(output=False)"
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|
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@ -313,7 +302,7 @@
|
|||
"outputs": [
|
||||
{
|
||||
"data": {
|
||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\n2kg8YwAAAABJRU5ErkJggg==\n",
|
||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAAAFzUkdC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\nVDIxOjExOjM4LTA0OjAwhCjsewAAAABJRU5ErkJggg==\n",
|
||||
"text/plain": [
|
||||
"<IPython.core.display.Image object>"
|
||||
]
|
||||
|
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@ -392,21 +381,21 @@
|
|||
"mesh.dimension = [1, 1, 1]\n",
|
||||
"mesh.lower_left = [-0.63, -0.63, -100.]\n",
|
||||
"mesh.width = [1.26, 1.26, 200.]\n",
|
||||
"mesh_filter = openmc.MeshFilter(mesh)\n",
|
||||
"meshsurface_filter = openmc.MeshSurfaceFilter(mesh)\n",
|
||||
"\n",
|
||||
"# Instantiate thermal, fast, and total leakage tallies\n",
|
||||
"leak = openmc.Tally(name='leakage')\n",
|
||||
"leak.filters = [mesh_filter]\n",
|
||||
"leak.filters = [meshsurface_filter]\n",
|
||||
"leak.scores = ['current']\n",
|
||||
"tallies_file.append(leak)\n",
|
||||
"\n",
|
||||
"thermal_leak = openmc.Tally(name='thermal leakage')\n",
|
||||
"thermal_leak.filters = [mesh_filter, openmc.EnergyFilter([0., 0.625])]\n",
|
||||
"thermal_leak.filters = [meshsurface_filter, openmc.EnergyFilter([0., 0.625])]\n",
|
||||
"thermal_leak.scores = ['current']\n",
|
||||
"tallies_file.append(thermal_leak)\n",
|
||||
"\n",
|
||||
"fast_leak = openmc.Tally(name='fast leakage')\n",
|
||||
"fast_leak.filters = [mesh_filter, openmc.EnergyFilter([0.625, 20.0e6])]\n",
|
||||
"fast_leak.filters = [meshsurface_filter, openmc.EnergyFilter([0.625, 20.0e6])]\n",
|
||||
"fast_leak.scores = ['current']\n",
|
||||
"tallies_file.append(fast_leak)"
|
||||
]
|
||||
|
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@ -504,11 +493,11 @@
|
|||
"name": "stderr",
|
||||
"output_type": "stream",
|
||||
"text": [
|
||||
"/home/romano/openmc/openmc/mixin.py:61: IDWarning: Another EnergyFilter instance already exists with id=6.\n",
|
||||
"/home/liangjg/.local/lib/python3.5/site-packages/openmc-0.10.0-py3.5.egg/openmc/mixin.py:71: IDWarning: Another Filter instance already exists with id=6.\n",
|
||||
" warn(msg, IDWarning)\n",
|
||||
"/home/romano/openmc/openmc/mixin.py:61: IDWarning: Another CellFilter instance already exists with id=3.\n",
|
||||
"/home/liangjg/.local/lib/python3.5/site-packages/openmc-0.10.0-py3.5.egg/openmc/mixin.py:71: IDWarning: Another Filter instance already exists with id=3.\n",
|
||||
" warn(msg, IDWarning)\n",
|
||||
"/home/romano/openmc/openmc/mixin.py:61: IDWarning: Another CellFilter instance already exists with id=2.\n",
|
||||
"/home/liangjg/.local/lib/python3.5/site-packages/openmc-0.10.0-py3.5.egg/openmc/mixin.py:71: IDWarning: Another Filter instance already exists with id=2.\n",
|
||||
" warn(msg, IDWarning)\n"
|
||||
]
|
||||
}
|
||||
|
|
@ -563,24 +552,25 @@
|
|||
" %%%%%%%%%%%\n",
|
||||
"\n",
|
||||
" | The OpenMC Monte Carlo Code\n",
|
||||
" Copyright | 2011-2017 Massachusetts Institute of Technology\n",
|
||||
" Copyright | 2011-2018 Massachusetts Institute of Technology\n",
|
||||
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
|
||||
" Version | 0.9.0\n",
|
||||
" Git SHA1 | 9b7cebf7bc34d60e0f1750c3d6cb103df11e8dc4\n",
|
||||
" Date/Time | 2017-12-04 20:43:15\n",
|
||||
" OpenMP Threads | 4\n",
|
||||
" Version | 0.10.0\n",
|
||||
" Git SHA1 | 47fbf8282ea94c138f75219bd10fdb31501d3fb7\n",
|
||||
" Date/Time | 2018-04-03 21:12:27\n",
|
||||
" MPI Processes | 1\n",
|
||||
" OpenMP Threads | 20\n",
|
||||
"\n",
|
||||
" Reading settings XML file...\n",
|
||||
" Reading cross sections XML file...\n",
|
||||
" Reading materials XML file...\n",
|
||||
" Reading geometry XML file...\n",
|
||||
" Building neighboring cells lists for each surface...\n",
|
||||
" Reading U235 from /home/romano/openmc/scripts/nndc_hdf5/U235.h5\n",
|
||||
" Reading U238 from /home/romano/openmc/scripts/nndc_hdf5/U238.h5\n",
|
||||
" Reading O16 from /home/romano/openmc/scripts/nndc_hdf5/O16.h5\n",
|
||||
" Reading H1 from /home/romano/openmc/scripts/nndc_hdf5/H1.h5\n",
|
||||
" Reading B10 from /home/romano/openmc/scripts/nndc_hdf5/B10.h5\n",
|
||||
" Reading Zr90 from /home/romano/openmc/scripts/nndc_hdf5/Zr90.h5\n",
|
||||
" Reading U235 from /home/liangjg/nucdata/nndc_hdf5/U235.h5\n",
|
||||
" Reading U238 from /home/liangjg/nucdata/nndc_hdf5/U238.h5\n",
|
||||
" Reading O16 from /home/liangjg/nucdata/nndc_hdf5/O16.h5\n",
|
||||
" Reading H1 from /home/liangjg/nucdata/nndc_hdf5/H1.h5\n",
|
||||
" Reading B10 from /home/liangjg/nucdata/nndc_hdf5/B10.h5\n",
|
||||
" Reading Zr90 from /home/liangjg/nucdata/nndc_hdf5/Zr90.h5\n",
|
||||
" Maximum neutron transport energy: 2.00000E+07 eV for U235\n",
|
||||
" Reading tallies XML file...\n",
|
||||
" Writing summary.h5 file...\n",
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||||
|
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@ -614,20 +604,20 @@
|
|||
"\n",
|
||||
" =======================> TIMING STATISTICS <=======================\n",
|
||||
"\n",
|
||||
" Total time for initialization = 5.6782E-01 seconds\n",
|
||||
" Reading cross sections = 5.3276E-01 seconds\n",
|
||||
" Total time in simulation = 6.4149E+00 seconds\n",
|
||||
" Time in transport only = 6.2767E+00 seconds\n",
|
||||
" Time in inactive batches = 6.8747E-01 seconds\n",
|
||||
" Time in active batches = 5.7274E+00 seconds\n",
|
||||
" Time synchronizing fission bank = 2.7492E-03 seconds\n",
|
||||
" Sampling source sites = 1.9584E-03 seconds\n",
|
||||
" SEND/RECV source sites = 7.4113E-04 seconds\n",
|
||||
" Time accumulating tallies = 1.0576E-04 seconds\n",
|
||||
" Total time for finalization = 2.2075E-03 seconds\n",
|
||||
" Total time elapsed = 7.0056E+00 seconds\n",
|
||||
" Calculation Rate (inactive) = 18182.5 neutrons/second\n",
|
||||
" Calculation Rate (active) = 6547.45 neutrons/second\n",
|
||||
" Total time for initialization = 4.9090E-01 seconds\n",
|
||||
" Reading cross sections = 4.2387E-01 seconds\n",
|
||||
" Total time in simulation = 1.4928E+00 seconds\n",
|
||||
" Time in transport only = 1.3545E+00 seconds\n",
|
||||
" Time in inactive batches = 1.3625E-01 seconds\n",
|
||||
" Time in active batches = 1.3565E+00 seconds\n",
|
||||
" Time synchronizing fission bank = 2.4053E-03 seconds\n",
|
||||
" Sampling source sites = 1.6466E-03 seconds\n",
|
||||
" SEND/RECV source sites = 5.6159E-04 seconds\n",
|
||||
" Time accumulating tallies = 3.3647E-04 seconds\n",
|
||||
" Total time for finalization = 1.6066E-02 seconds\n",
|
||||
" Total time elapsed = 2.0336E+00 seconds\n",
|
||||
" Calculation Rate (inactive) = 91743.2 neutrons/second\n",
|
||||
" Calculation Rate (active) = 27644.5 neutrons/second\n",
|
||||
"\n",
|
||||
" ============================> RESULTS <============================\n",
|
||||
"\n",
|
||||
|
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@ -638,16 +628,6 @@
|
|||
" Leakage Fraction = 0.01717 +/- 0.00107\n",
|
||||
"\n"
|
||||
]
|
||||
},
|
||||
{
|
||||
"data": {
|
||||
"text/plain": [
|
||||
"0"
|
||||
]
|
||||
},
|
||||
"execution_count": 21,
|
||||
"metadata": {},
|
||||
"output_type": "execute_result"
|
||||
}
|
||||
],
|
||||
"source": [
|
||||
|
|
@ -741,8 +721,7 @@
|
|||
"\n",
|
||||
"# Get the leakage tally\n",
|
||||
"leak = sp.get_tally(name='leakage')\n",
|
||||
"leak = leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
|
||||
"leak = leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
|
||||
"leak = leak.summation(filter_type=openmc.MeshSurfaceFilter, remove_filter=True)\n",
|
||||
"\n",
|
||||
"# Compute k-infinity using tally arithmetic\n",
|
||||
"keff = fiss_rate / (abs_rate + leak)\n",
|
||||
|
|
@ -812,8 +791,7 @@
|
|||
"# Compute resonance escape probability using tally arithmetic\n",
|
||||
"therm_abs_rate = sp.get_tally(name='therm. abs. rate')\n",
|
||||
"thermal_leak = sp.get_tally(name='thermal leakage')\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type=openmc.MeshSurfaceFilter, remove_filter=True)\n",
|
||||
"res_esc = (therm_abs_rate + thermal_leak) / (abs_rate + thermal_leak)\n",
|
||||
"res_esc.get_pandas_dataframe()"
|
||||
]
|
||||
|
|
|
|||
49
examples/python/pincell_depletion/chain_simple.xml
Normal file
49
examples/python/pincell_depletion/chain_simple.xml
Normal file
|
|
@ -0,0 +1,49 @@
|
|||
<?xml version="1.0"?>
|
||||
<depletion_chain>
|
||||
<nuclide name="I135" decay_modes="1" reactions="1" half_life="2.36520E+04">
|
||||
<decay type="beta" target="Xe135" branching_ratio="1.0" />
|
||||
<reaction type="(n,gamma)" Q="0.0" target="Xe136" /> <!-- Not precisely true, but whatever -->
|
||||
</nuclide>
|
||||
<nuclide name="Xe135" decay_modes="1" reactions="1" half_life="3.29040E+04">
|
||||
<decay type=" beta" target="Cs135" branching_ratio="1.0" />
|
||||
<reaction type="(n,gamma)" Q="0.0" target="Xe136" />
|
||||
</nuclide>
|
||||
<nuclide name="Xe136" decay_modes="0" reactions="0" />
|
||||
<nuclide name="Cs135" decay_modes="0" reactions="0" />
|
||||
<nuclide name="Gd157" decay_modes="0" reactions="1" >
|
||||
<reaction type="(n,gamma)" Q="0.0" target="Nothing" />
|
||||
</nuclide>
|
||||
<nuclide name="Gd156" decay_modes="0" reactions="1">
|
||||
<reaction type="(n,gamma)" Q="0.0" target="Gd157" />
|
||||
</nuclide>
|
||||
<nuclide name="U234" decay_modes="0" reactions="1">
|
||||
<reaction type="fission" Q="191840000."/>
|
||||
<neutron_fission_yields>
|
||||
<energies>2.53000e-02</energies>
|
||||
<fission_yields energy="2.53000e-02">
|
||||
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
|
||||
<data>1.093250e-04 2.087260e-04 2.780820e-02 6.759540e-03 2.392300e-02 4.356330e-05</data>
|
||||
</fission_yields>
|
||||
</neutron_fission_yields>
|
||||
</nuclide>
|
||||
<nuclide name="U235" decay_modes="0" reactions="1">
|
||||
<reaction type="fission" Q="193410000."/>
|
||||
<neutron_fission_yields>
|
||||
<energies>2.53000e-02</energies>
|
||||
<fission_yields energy="2.53000e-02">
|
||||
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
|
||||
<data>6.142710e-5 1.483250e-04 0.0292737 0.002566345 0.0219242 4.9097e-6</data>
|
||||
</fission_yields>
|
||||
</neutron_fission_yields>
|
||||
</nuclide>
|
||||
<nuclide name="U238" decay_modes="0" reactions="1">
|
||||
<reaction type="fission" Q="197790000."/>
|
||||
<neutron_fission_yields>
|
||||
<energies>2.53000e-02</energies>
|
||||
<fission_yields energy="2.53000e-02">
|
||||
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
|
||||
<data>4.141120e-04 7.605360e-04 0.0135457 0.00026864 0.0024432 3.7100E-07</data>
|
||||
</fission_yields>
|
||||
</neutron_fission_yields>
|
||||
</nuclide>
|
||||
</depletion_chain>
|
||||
148
examples/python/pincell_depletion/run_depletion.py
Normal file
148
examples/python/pincell_depletion/run_depletion.py
Normal file
|
|
@ -0,0 +1,148 @@
|
|||
import openmc
|
||||
import openmc.deplete
|
||||
import numpy as np
|
||||
|
||||
###############################################################################
|
||||
# Simulation Input File Parameters
|
||||
###############################################################################
|
||||
|
||||
# OpenMC simulation parameters
|
||||
batches = 100
|
||||
inactive = 10
|
||||
particles = 1000
|
||||
|
||||
# Depletion simulation parameters
|
||||
time_step = 1*24*60*60 # s
|
||||
final_time = 15*24*60*60 # s
|
||||
time_steps = np.full(final_time // time_step, time_step)
|
||||
|
||||
chain_file = './chain_simple.xml'
|
||||
power = 174 # W/cm, for 2D simulations only (use W for 3D)
|
||||
|
||||
###############################################################################
|
||||
# Define materials
|
||||
###############################################################################
|
||||
|
||||
# Instantiate some Materials and register the appropriate Nuclides
|
||||
uo2 = openmc.Material(material_id=1, name='UO2 fuel at 2.4% wt enrichment')
|
||||
uo2.set_density('g/cm3', 10.29769)
|
||||
uo2.add_element('U', 1., enrichment=2.4)
|
||||
uo2.add_element('O', 2.)
|
||||
uo2.depletable = True
|
||||
|
||||
helium = openmc.Material(material_id=2, name='Helium for gap')
|
||||
helium.set_density('g/cm3', 0.001598)
|
||||
helium.add_element('He', 2.4044e-4)
|
||||
|
||||
zircaloy = openmc.Material(material_id=3, name='Zircaloy 4')
|
||||
zircaloy.set_density('g/cm3', 6.55)
|
||||
zircaloy.add_element('Sn', 0.014 , 'wo')
|
||||
zircaloy.add_element('Fe', 0.00165, 'wo')
|
||||
zircaloy.add_element('Cr', 0.001 , 'wo')
|
||||
zircaloy.add_element('Zr', 0.98335, 'wo')
|
||||
|
||||
borated_water = openmc.Material(material_id=4, name='Borated water')
|
||||
borated_water.set_density('g/cm3', 0.740582)
|
||||
borated_water.add_element('B', 4.0e-5)
|
||||
borated_water.add_element('H', 5.0e-2)
|
||||
borated_water.add_element('O', 2.4e-2)
|
||||
borated_water.add_s_alpha_beta('c_H_in_H2O')
|
||||
|
||||
###############################################################################
|
||||
# Exporting to OpenMC geometry.xml file
|
||||
###############################################################################
|
||||
|
||||
# Instantiate ZCylinder surfaces
|
||||
fuel_or = openmc.ZCylinder(surface_id=1, x0=0, y0=0, R=0.39218, name='Fuel OR')
|
||||
clad_ir = openmc.ZCylinder(surface_id=2, x0=0, y0=0, R=0.40005, name='Clad IR')
|
||||
clad_or = openmc.ZCylinder(surface_id=3, x0=0, y0=0, R=0.45720, name='Clad OR')
|
||||
left = openmc.XPlane(surface_id=4, x0=-0.62992, name='left')
|
||||
right = openmc.XPlane(surface_id=5, x0=0.62992, name='right')
|
||||
bottom = openmc.YPlane(surface_id=6, y0=-0.62992, name='bottom')
|
||||
top = openmc.YPlane(surface_id=7, y0=0.62992, name='top')
|
||||
|
||||
left.boundary_type = 'reflective'
|
||||
right.boundary_type = 'reflective'
|
||||
top.boundary_type = 'reflective'
|
||||
bottom.boundary_type = 'reflective'
|
||||
|
||||
# Instantiate Cells
|
||||
fuel = openmc.Cell(cell_id=1, name='cell 1')
|
||||
gap = openmc.Cell(cell_id=2, name='cell 2')
|
||||
clad = openmc.Cell(cell_id=3, name='cell 3')
|
||||
water = openmc.Cell(cell_id=4, name='cell 4')
|
||||
|
||||
# Use surface half-spaces to define regions
|
||||
fuel.region = -fuel_or
|
||||
gap.region = +fuel_or & -clad_ir
|
||||
clad.region = +clad_ir & -clad_or
|
||||
water.region = +clad_or & +left & -right & +bottom & -top
|
||||
|
||||
# Register Materials with Cells
|
||||
fuel.fill = uo2
|
||||
gap.fill = helium
|
||||
clad.fill = zircaloy
|
||||
water.fill = borated_water
|
||||
|
||||
# Instantiate Universe
|
||||
root = openmc.Universe(universe_id=0, name='root universe')
|
||||
|
||||
# Register Cells with Universe
|
||||
root.add_cells([fuel, gap, clad, water])
|
||||
|
||||
# Instantiate a Geometry, register the root Universe
|
||||
geometry = openmc.Geometry(root)
|
||||
|
||||
###############################################################################
|
||||
# Exporting to OpenMC materials.xml file
|
||||
###############################################################################
|
||||
|
||||
# Compute cell areas
|
||||
area = {}
|
||||
area[fuel] = np.pi * fuel_or.coefficients['R'] ** 2
|
||||
|
||||
# Set materials volume for depletion. Set to an area for 2D simulations
|
||||
uo2.volume = area[fuel]
|
||||
|
||||
###############################################################################
|
||||
# Exporting to OpenMC settings.xml file
|
||||
###############################################################################
|
||||
|
||||
# Instantiate a Settings object, set all runtime parameters, and export to XML
|
||||
settings_file = openmc.Settings()
|
||||
settings_file.batches = batches
|
||||
settings_file.inactive = inactive
|
||||
settings_file.particles = particles
|
||||
|
||||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
settings_file.source = openmc.source.Source(space=uniform_dist)
|
||||
|
||||
entropy_mesh = openmc.Mesh()
|
||||
entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50]
|
||||
entropy_mesh.upper_right = [0.39218, 0.39218, 1.e50]
|
||||
entropy_mesh.dimension = [10, 10, 1]
|
||||
settings_file.entropy_mesh = entropy_mesh
|
||||
|
||||
###############################################################################
|
||||
# Initialize and run depletion calculation
|
||||
###############################################################################
|
||||
|
||||
op = openmc.deplete.Operator(geometry, settings_file, chain_file)
|
||||
|
||||
# Perform simulation using the predictor algorithm
|
||||
openmc.deplete.integrator.predictor(op, time_steps, power)
|
||||
|
||||
###############################################################################
|
||||
# Read depletion calculation results
|
||||
###############################################################################
|
||||
|
||||
# Open results file
|
||||
results = openmc.deplete.ResultsList("depletion_results.h5")
|
||||
|
||||
# Obtain K_eff as a function of time
|
||||
time, keff = results.get_eigenvalue()
|
||||
|
||||
# Obtain U235 concentration as a function of time
|
||||
time, n_U235 = results.get_atoms('1', 'U235')
|
||||
|
|
@ -2853,6 +2853,9 @@ contains
|
|||
call fatal_error("Cannot tally other scores in the &
|
||||
&same tally as surface currents")
|
||||
end if
|
||||
else
|
||||
call fatal_error("Cannot tally currents without surface &
|
||||
&type filters")
|
||||
end if
|
||||
|
||||
case ('events')
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue