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Merge pull request #803 from nelsonag/nonu

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Removal of Nu* MGXS classes.
This commit is contained in:
Will Boyd 2017-02-26 15:44:19 -05:00 • committed by GitHub
commit 1bd3cde52b
6 changed files with 479 additions and 1163 deletions
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227
docs/source/pythonapi/examples/mdgxs-part-i.ipynb
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docs/source/pythonapi/examples/mgxs-part-i.ipynb
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@ -369,21 +369,21 @@
"\n",
"* `TotalXS`\n",
"* `TransportXS`\n",
"* `NuTransportXS`\n",
"* `AbsorptionXS`\n",
"* `CaptureXS`\n",
"* `FissionXS`\n",
"* `NuFissionXS`\n",
"* `KappaFissionXS`\n",
"* `ScatterXS`\n",
"* `NuScatterXS`\n",
"* `ScatterMatrixXS`\n",
"* `NuScatterMatrixXS`\n",
"* `Chi`\n",
"* `ChiPrompt`\n",
"* `InverseVelocity`\n",
"* `PromptNuFissionXS`\n",
"\n",
"Of course, we are aware that the fission cross section (`FissionXS`) can sometimes be paired with the fission neutron multiplication to become $\\nu\\sigma_f$. This can be accomodated in to the `FissionXS` class by setting the `nu` parameter to `True` as shown below.\n",
"\n",
"Additionally, scattering reactions (like (n,2n)) can also be defined to take in to account the neutron multiplication to become $\\nu\\sigma_s$. This can be accomodated in the the transport (`TransportXS`), scattering (`ScatterXS`), and scattering-matrix (`ScatterMatrixXS`) cross sections types by setting the `nu` parameter to `True` as shown below.\n",
"\n",
"These classes provide us with an interface to generate the tally inputs as well as perform post-processing of OpenMC's tally data to compute the respective multi-group cross sections. In this case, let's create the multi-group total, absorption and scattering cross sections with our 2-group structure."
]
},
@ -398,7 +398,11 @@
"# Instantiate a few different sections\n",
"total = mgxs.TotalXS(domain=cell, groups=groups)\n",
"absorption = mgxs.AbsorptionXS(domain=cell, groups=groups)\n",
"scattering = mgxs.ScatterXS(domain=cell, groups=groups)"
"scattering = mgxs.ScatterXS(domain=cell, groups=groups)\n",
"\n",
"# Note that if we wanted to incorporate neutron multiplication in the\n",
"# scattering cross section we would write the previous line as:\n",
"# scattering = mgxs.ScatterXS(domain=cell, groups=groups, nu=True)"
]
},
{
@ -520,8 +524,8 @@
" Copyright | 2011-2017 Massachusetts Institute of Technology\n",
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
" Version | 0.8.0\n",
" Git SHA1 | 54b65c8bda6af5788bd762b8cf9855d1a8008238\n",
" Date/Time | 2017-02-12 13:36:24\n",
" Git SHA1 | 60a1f157dae88b62e1865a5fe3efd7ef0773a068\n",
" Date/Time | 2017-02-25 14:26:54\n",
" OpenMP Threads | 8\n",
"\n",
" ===========================================================================\n",
@ -592,7 +596,7 @@
" 42/1 1.13779 1.16177 +/- 0.00531\n",
" 43/1 1.15066 1.16143 +/- 0.00516\n",
" 44/1 1.12174 1.16026 +/- 0.00514\n",
" 45/1 1.17479 1.16068 +/- 0.00501\n",
" 45/1 1.17478 1.16068 +/- 0.00501\n",
" 46/1 1.14146 1.16014 +/- 0.00489\n",
" 47/1 1.20464 1.16135 +/- 0.00491\n",
" 48/1 1.15119 1.16108 +/- 0.00479\n",
@ -607,20 +611,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 4.1327E-01 seconds\n",
" Reading cross sections = 3.2638E-01 seconds\n",
" Total time in simulation = 2.2324E+00 seconds\n",
" Time in transport only = 2.1226E+00 seconds\n",
" Time in inactive batches = 3.0650E-01 seconds\n",
" Time in active batches = 1.9259E+00 seconds\n",
" Time synchronizing fission bank = 2.7640E-03 seconds\n",
" Sampling source sites = 2.0198E-03 seconds\n",
" SEND/RECV source sites = 7.0929E-04 seconds\n",
" Time accumulating tallies = 4.5355E-05 seconds\n",
" Total time for finalization = 4.1885E-04 seconds\n",
" Total time elapsed = 2.6534E+00 seconds\n",
" Calculation Rate (inactive) = 81567.1 neutrons/second\n",
" Calculation Rate (active) = 51923.2 neutrons/second\n",
" Total time for initialization = 3.5070E-01 seconds\n",
" Reading cross sections = 2.4151E-01 seconds\n",
" Total time in simulation = 2.3276E+00 seconds\n",
" Time in transport only = 2.2350E+00 seconds\n",
" Time in inactive batches = 2.5677E-01 seconds\n",
" Time in active batches = 2.0708E+00 seconds\n",
" Time synchronizing fission bank = 2.7683E-03 seconds\n",
" Sampling source sites = 2.0233E-03 seconds\n",
" SEND/RECV source sites = 7.1007E-04 seconds\n",
" Time accumulating tallies = 5.0753E-05 seconds\n",
" Total time for finalization = 3.8695E-04 seconds\n",
" Total time elapsed = 2.6857E+00 seconds\n",
" Calculation Rate (inactive) = 97364.6 neutrons/second\n",
" Calculation Rate (active) = 48290.8 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -901,7 +905,7 @@
" <td>6.250000e-01</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-2.664535e-15</td>\n",
" <td>-5.551115e-15</td>\n",
" <td>0.011292</td>\n",
" </tr>\n",
" <tr>\n",
@ -911,7 +915,7 @@
" <td>2.000000e+07</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-3.330669e-16</td>\n",
" <td>-1.110223e-16</td>\n",
" <td>0.002570</td>\n",
" </tr>\n",
" </tbody>\n",
@ -924,8 +928,8 @@
"1 1 6.25e-01 2.00e+07 total \n",
"\n",
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... -2.66e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -3.33e-16 2.57e-03 "
"0 (((total / flux) - (absorption / flux)) - (sca... -5.55e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -1.11e-16 2.57e-03 "
]
},
"execution_count": 22,

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docs/source/pythonapi/examples/mgxs-part-ii.ipynb
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docs/source/pythonapi/examples/mgxs-part-iii.ipynb
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1154
openmc/mgxs/mgxs.py
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openmc/mgxs_library.py
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@ -1074,12 +1074,12 @@ class XSdata(object):
def set_nu_fission_mgxs(self, nu_fission, temperature=294.,
nuclide='total', xs_type='macro', subdomain=None):
"""This method allows for an openmc.mgxs.NuFissionXS
"""This method allows for an openmc.mgxs.FissionXS
to be used to set the nu-fission cross section for this XSdata object.
Parameters
----------
nu_fission: openmc.mgxs.NuFissionXS
nu_fission: openmc.mgxs.FissionXS
MGXS Object containing the nu-fission cross section
for the domain of interest.
temperature : float
@ -1102,8 +1102,10 @@ class XSdata(object):
"""
check_type('nu_fission', nu_fission, (openmc.mgxs.NuFissionXS,
check_type('nu_fission', nu_fission, (openmc.mgxs.FissionXS,
openmc.mgxs.NuFissionMatrixXS))
if isinstance(nu_fission, openmc.mgxs.FissionXS):
check_value('nu', nu_fission.nu, [True])
check_value('energy_groups', nu_fission.energy_groups,
[self.energy_groups])
check_value('domain_type', nu_fission.domain_type,
@ -1124,13 +1126,13 @@ class XSdata(object):
subdomain=None):
"""Sets the prompt-nu-fission cross section.
This method allows for an openmc.mgxs.PromptNuFissionXS or
openmc.mgxs.PromptNuFissionMatrixXS to be used to set the
prompt-nu-fission cross section for this XSdata object.
This method allows for an openmc.mgxs.FissionXS or
openmc.mgxs.NuFissionMatrixXS to be used to set the prompt-nu-fission
cross section for this XSdata object.
Parameters
----------
prompt_nu_fission: openmc.mgxs.PromptNuFissionXS or openmc.mgxs.PromptNuFissionMatrixXS
prompt_nu_fission: openmc.mgxs.FissionXS or openmc.mgxs.NuFissionMatrixXS
MGXS Object containing the prompt-nu-fission cross section
for the domain of interest.
temperature : float
@ -1154,8 +1156,8 @@ class XSdata(object):
"""
check_type('prompt_nu_fission', prompt_nu_fission,
(openmc.mgxs.PromptNuFissionXS,
openmc.mgxs.PromptNuFissionMatrixXS))
(openmc.mgxs.FissionXS, openmc.mgxs.NuFissionMatrixXS))
check_value('prompt', prompt_nu_fission.prompt, [True])
check_value('energy_groups', prompt_nu_fission.energy_groups,
[self.energy_groups])
check_value('domain_type', prompt_nu_fission.domain_type,
@ -1307,12 +1309,12 @@ class XSdata(object):
def set_chi_prompt_mgxs(self, chi_prompt, temperature=294.,
nuclide='total', xs_type='macro', subdomain=None):
"""This method allows for an openmc.mgxs.ChiPrompt
to be used to set chi-prompt for this XSdata object.
"""This method allows for an openmc.mgxs.Chi to be used to set
chi-prompt for this XSdata object.
Parameters
----------
chi_prompt: openmc.mgxs.ChiPrompt
chi_prompt: openmc.mgxs.Chi
MGXS Object containing chi-prompt for the domain of interest.
temperature : float
Temperature (in units of Kelvin) of the provided dataset. Defaults
@ -1334,7 +1336,8 @@ class XSdata(object):
"""
check_type('chi_prompt', chi_prompt, openmc.mgxs.ChiPrompt)
check_type('chi_prompt', chi_prompt, openmc.mgxs.Chi)
check_value('prompt', chi_prompt.prompt, [True])
check_value('energy_groups', chi_prompt.energy_groups,
[self.energy_groups])
check_value('domain_type', chi_prompt.domain_type,
@ -1598,7 +1601,7 @@ class XSdata(object):
"""
check_type('nuscatter', nuscatter, (openmc.mgxs.NuScatterMatrixXS,
check_type('nuscatter', nuscatter, (openmc.mgxs.ScatterMatrixXS,
openmc.mgxs.MultiplicityMatrixXS))
check_value('energy_groups', nuscatter.energy_groups,
[self.energy_groups])