mirror of
https://github.com/openmc-dev/openmc.git
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Merge remote-tracking branch 'upstream/develop' into diff_tally6
This commit is contained in:
Sterling Harper
commit
902286a674
105 changed files with 1833 additions and 1868 deletions
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@ -30,7 +30,7 @@ MGXS Library Specification
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|||
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:Attributes: - **groups** (*int*) -- Number of energy groups
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- **group structure** (*double[]*) -- Monotonically increasing
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||||
list of group boundaries, in units of MeV. The length of this
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||||
list of group boundaries, in units of eV. The length of this
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||||
array should be the number of groups plus 1.
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||||
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**/<library name>/**
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@ -77,8 +77,8 @@ data for the nuclide or material that it represents.
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**/<library name>/kTs/**
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:Datasets:
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||||
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
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||||
:Datasets:
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||||
- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
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TTT (in Kelvin), rounded to the nearest integer
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**/<library name>/<TTT>K/**
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@ -161,4 +161,4 @@ Data specific to neutron scattering for the temperature <TTT>K
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1.0) will be assumed.
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The pre-flattened array is shapes consistent with `scatter_matrix`
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except the "[Order]" dimension in `scatter_shape` is ignored since
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this data is assumed isotropic.
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this data is assumed isotropic.
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@ -8,6 +8,10 @@ Nuclear Data File Format
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Incident Neutron Data
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---------------------
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**/**
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:Attributes:
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- **version** (*int[2]*) -- Major and minor version of the data
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**/<nuclide name>/**
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@ -27,14 +31,14 @@ temperature-dependent data set. For example, the data set corresponding to
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300 Kelvin would be located at `300K`.
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:Datasets:
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- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
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- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
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TTT (in Kelvin)
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**/<nuclide name>/reactions/reaction_<mt>/**
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:Attributes: - **mt** (*int*) -- ENDF MT reaction number
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- **label** (*char[]*) -- Name of the reaction
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- **Q_value** (*double*) -- Q value in MeV
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||||
- **Q_value** (*double*) -- Q value in eV
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- **center_of_mass** (*int*) -- Whether the reference frame for
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scattering is center-of-mass (1) or laboratory (0)
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- **n_product** (*int*) -- Number of reaction products
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@ -113,6 +117,11 @@ temperature-dependent data set. For example, the data set corresponding to
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Thermal Neutron Scattering Data
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-------------------------------
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**/**
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:Attributes:
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- **version** (*int[2]*) -- Major and minor version of the data
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**/<thermal name>/**
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:Attributes: - **atomic_weight_ratio** (*double*) -- Mass in units of neutron masses
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@ -129,7 +138,7 @@ temperature-dependent data set. For example, the data set corresponding to
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|||
300 Kelvin would be located at `300K`.
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:Datasets:
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||||
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
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||||
- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
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TTT (in Kelvin)
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**/<thermal name>/elastic/<TTT>K/**
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@ -333,7 +342,7 @@ N-Body Phase Space
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- **n_particles** (*int*) -- Number of product particles
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- **atomic_weight_ratio** (*double*) -- Atomic weight ratio of the
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target nuclide in neutron masses
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- **q_value** (*double*) -- Q value for the reaction in MeV
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- **q_value** (*double*) -- Q value for the reaction in eV
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.. _energy_distribution:
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@ -346,7 +355,7 @@ Maxwell
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:Object type: Group
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:Attributes: - **type** (*char[]*) -- 'maxwell'
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- **u** (*double*) -- Restriction energy in MeV
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||||
- **u** (*double*) -- Restriction energy in eV
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:Datasets:
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||||
- **theta** (:ref:`tabulated <1d_tabulated>`) -- Maxwellian
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||||
temperature as a function of energy
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@ -356,7 +365,7 @@ Evaporation
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:Object type: Group
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||||
:Attributes: - **type** (*char[]*) -- 'evaporation'
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- **u** (*double*) -- Restriction energy in MeV
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||||
- **u** (*double*) -- Restriction energy in eV
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||||
:Datasets:
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- **theta** (:ref:`tabulated <1d_tabulated>`) -- Evaporation
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temperature as a function of energy
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@ -366,7 +375,7 @@ Watt Fission Spectrum
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|
||||
:Object type: Group
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||||
:Attributes: - **type** (*char[]*) -- 'watt'
|
||||
- **u** (*double*) -- Restriction energy in MeV
|
||||
- **u** (*double*) -- Restriction energy in eV
|
||||
:Datasets: - **a** (:ref:`tabulated <1d_tabulated>`) -- Watt parameter :math:`a`
|
||||
as a function of incident energy
|
||||
- **b** (:ref:`tabulated <1d_tabulated>`) -- Watt parameter :math:`b`
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@ -386,7 +395,7 @@ Discrete Photon
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:Object type: Group
|
||||
:Attributes: - **type** (*char[]*) -- 'discrete_photon'
|
||||
- **primary_flag** (*int*) -- Whether photon is a primary
|
||||
- **energy** (*double*) -- Photon energy in MeV
|
||||
- **energy** (*double*) -- Photon energy in eV
|
||||
- **atomic_weight_ratio** (*double*) -- Atomic weight ratio of
|
||||
target nuclide in neutron masses
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@ -396,7 +405,7 @@ Level Inelastic
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:Object type: Group
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||||
:Attributes: - **type** (*char[]*) -- 'level'
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||||
- **threshold** (*double*) -- Energy threshold in the laboratory
|
||||
system in MeV
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||||
system in eV
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||||
- **mass_ratio** (*double*) -- :math:`(A/(A + 1))^2`
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||||
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Continuous Tabular
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@ -46,7 +46,7 @@ The current revision of the particle restart file format is 1.
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**/energy** (*double*)
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Energy of the particle in MeV for continuous-energy mode, or the energy
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Energy of the particle in eV for continuous-energy mode, or the energy
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||||
group of the particle for multi-group mode.
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**/xyz** (*double[3]*)
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File diff suppressed because one or more lines are too long
File diff suppressed because one or more lines are too long
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@ -8,9 +8,7 @@
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"\n",
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||||
"* **General equations** for scalar-flux averaged multi-group cross sections\n",
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"* Creation of multi-group cross sections for an **infinite homogeneous medium**\n",
|
||||
"* Use of **tally arithmetic** to manipulate multi-group cross sections\n",
|
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"\n",
|
||||
"**Note:** This Notebook illustrates the use of [Pandas](http://pandas.pydata.org/) `DataFrames` to containerize multi-group cross section data. We recommend using [Pandas](http://pandas.pydata.org/) >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of [Pandas](http://pandas.pydata.org/)."
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||||
"* Use of **tally arithmetic** to manipulate multi-group cross sections"
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||||
]
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},
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{
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@ -360,7 +358,7 @@
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"source": [
|
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"# Instantiate a 2-group EnergyGroups object\n",
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"groups = mgxs.EnergyGroups()\n",
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"groups.group_edges = np.array([0., 0.625e-6, 20.])"
|
||||
"groups.group_edges = np.array([0., 0.625, 20.0e6])"
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||||
]
|
||||
},
|
||||
{
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@ -424,16 +422,16 @@
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|||
" \tID =\t10000\n",
|
||||
" \tName =\t\n",
|
||||
" \tFilters =\t\n",
|
||||
" \t\tcell\t[1]\n",
|
||||
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
|
||||
" \t\tCellFilter\t[1]\n",
|
||||
" \t\tEnergyFilter\t[ 0.00000000e+00 6.25000000e-01 2.00000000e+07]\n",
|
||||
" \tNuclides =\ttotal \n",
|
||||
" \tScores =\t['flux']\n",
|
||||
" \tEstimator =\ttracklength), ('absorption', Tally\n",
|
||||
" \tID =\t10001\n",
|
||||
" \tName =\t\n",
|
||||
" \tFilters =\t\n",
|
||||
" \t\tcell\t[1]\n",
|
||||
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
|
||||
" \t\tCellFilter\t[1]\n",
|
||||
" \t\tEnergyFilter\t[ 0.00000000e+00 6.25000000e-01 2.00000000e+07]\n",
|
||||
" \tNuclides =\ttotal \n",
|
||||
" \tScores =\t['absorption']\n",
|
||||
" \tEstimator =\ttracklength)])"
|
||||
|
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@ -526,8 +524,8 @@
|
|||
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
|
||||
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
|
||||
" Version | 0.8.0\n",
|
||||
" Git SHA1 | fbebf7bf709fe2fe1813af95bff9b29c0d59312c\n",
|
||||
" Date/Time | 2016-08-31 10:40:13\n",
|
||||
" Git SHA1 | da5563eddb5f2c2d6b2c9839d518de40962b78f2\n",
|
||||
" Date/Time | 2016-10-31 12:23:45\n",
|
||||
" OpenMP Threads | 4\n",
|
||||
"\n",
|
||||
" ===========================================================================\n",
|
||||
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@ -536,14 +534,14 @@
|
|||
"\n",
|
||||
" Reading settings XML file...\n",
|
||||
" Reading geometry XML file...\n",
|
||||
" Reading cross sections XML file...\n",
|
||||
" Reading materials XML file...\n",
|
||||
" Reading H1 from /home/romano/openmc/data/nndc_hdf5/H1.h5\n",
|
||||
" Reading O16 from /home/romano/openmc/data/nndc_hdf5/O16.h5\n",
|
||||
" Reading U235 from /home/romano/openmc/data/nndc_hdf5/U235.h5\n",
|
||||
" Reading U238 from /home/romano/openmc/data/nndc_hdf5/U238.h5\n",
|
||||
" Reading Zr90 from /home/romano/openmc/data/nndc_hdf5/Zr90.h5\n",
|
||||
" Maximum neutron transport energy: 20.0000 MeV for H1\n",
|
||||
" Reading cross sections XML file...\n",
|
||||
" Reading H1 from /home/romano/openmc/scripts/nndc_hdf5/H1.h5\n",
|
||||
" Reading O16 from /home/romano/openmc/scripts/nndc_hdf5/O16.h5\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 Zr90 from /home/romano/openmc/scripts/nndc_hdf5/Zr90.h5\n",
|
||||
" Maximum neutron transport energy: 2.00000E+07 eV for H1\n",
|
||||
" Reading tallies XML file...\n",
|
||||
" Building neighboring cells lists for each surface...\n",
|
||||
" Initializing source particles...\n",
|
||||
|
|
@ -613,20 +611,20 @@
|
|||
"\n",
|
||||
" =======================> TIMING STATISTICS <=======================\n",
|
||||
"\n",
|
||||
" Total time for initialization = 3.9900E-01 seconds\n",
|
||||
" Reading cross sections = 2.6500E-01 seconds\n",
|
||||
" Total time in simulation = 1.1488E+01 seconds\n",
|
||||
" Time in transport only = 1.1152E+01 seconds\n",
|
||||
" Time in inactive batches = 1.2180E+00 seconds\n",
|
||||
" Time in active batches = 1.0270E+01 seconds\n",
|
||||
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
|
||||
" Sampling source sites = 3.0000E-03 seconds\n",
|
||||
" SEND/RECV source sites = 1.0000E-03 seconds\n",
|
||||
" Time accumulating tallies = 0.0000E+00 seconds\n",
|
||||
" Total time for finalization = 1.0000E-03 seconds\n",
|
||||
" Total time elapsed = 1.1901E+01 seconds\n",
|
||||
" Calculation Rate (inactive) = 20525.5 neutrons/second\n",
|
||||
" Calculation Rate (active) = 9737.10 neutrons/second\n",
|
||||
" Total time for initialization = 7.3858E-01 seconds\n",
|
||||
" Reading cross sections = 5.3599E-01 seconds\n",
|
||||
" Total time in simulation = 2.1031E+01 seconds\n",
|
||||
" Time in transport only = 1.9960E+01 seconds\n",
|
||||
" Time in inactive batches = 2.6543E+00 seconds\n",
|
||||
" Time in active batches = 1.8376E+01 seconds\n",
|
||||
" Time synchronizing fission bank = 5.8389E-03 seconds\n",
|
||||
" Sampling source sites = 4.2676E-03 seconds\n",
|
||||
" SEND/RECV source sites = 1.4523E-03 seconds\n",
|
||||
" Time accumulating tallies = 1.5633E-04 seconds\n",
|
||||
" Total time for finalization = 7.9179E-04 seconds\n",
|
||||
" Total time elapsed = 2.1784E+01 seconds\n",
|
||||
" Calculation Rate (inactive) = 9418.63 neutrons/second\n",
|
||||
" Calculation Rate (active) = 5441.81 neutrons/second\n",
|
||||
"\n",
|
||||
" ============================> RESULTS <============================\n",
|
||||
"\n",
|
||||
|
|
@ -745,8 +743,8 @@
|
|||
"\tDomain Type =\tcell\n",
|
||||
"\tDomain ID =\t1\n",
|
||||
"\tCross Sections [cm^-1]:\n",
|
||||
" Group 1 [6.25e-07 - 20.0 MeV]:\t6.81e-01 +/- 2.69e-01%\n",
|
||||
" Group 2 [0.0 - 6.25e-07 MeV]:\t1.40e+00 +/- 5.93e-01%\n",
|
||||
" Group 1 [0.625 - 20000000.0eV]:\t6.81e-01 +/- 2.69e-01%\n",
|
||||
" Group 2 [0.0 - 0.625 eV]:\t1.40e+00 +/- 5.93e-01%\n",
|
||||
"\n",
|
||||
"\n",
|
||||
"\n"
|
||||
|
|
@ -891,8 +889,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -903,21 +901,21 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
|
||||
" <td>-2.886580e-15</td>\n",
|
||||
" <td>-2.664535e-15</td>\n",
|
||||
" <td>0.011292</td>\n",
|
||||
" </tr>\n",
|
||||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
|
||||
" <td>-5.551115e-16</td>\n",
|
||||
" <td>-7.771561e-16</td>\n",
|
||||
" <td>0.002570</td>\n",
|
||||
" </tr>\n",
|
||||
" </tbody>\n",
|
||||
|
|
@ -925,13 +923,13 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-07 total \n",
|
||||
"1 1 6.25e-07 2.00e+01 total \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-01 total \n",
|
||||
"1 1 6.25e-01 2.00e+07 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 (((total / flux) - (absorption / flux)) - (sca... -2.89e-15 1.13e-02 \n",
|
||||
"1 (((total / flux) - (absorption / flux)) - (sca... -5.55e-16 2.57e-03 "
|
||||
"0 (((total / flux) - (absorption / flux)) - (sca... -2.66e-15 1.13e-02 \n",
|
||||
"1 (((total / flux) - (absorption / flux)) - (sca... -7.77e-16 2.57e-03 "
|
||||
]
|
||||
},
|
||||
"execution_count": 22,
|
||||
|
|
@ -970,8 +968,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -982,8 +980,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>((absorption / flux) / (total / flux))</td>\n",
|
||||
" <td>0.076115</td>\n",
|
||||
|
|
@ -992,8 +990,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>((absorption / flux) / (total / flux))</td>\n",
|
||||
" <td>0.019263</td>\n",
|
||||
|
|
@ -1004,9 +1002,9 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-07 total \n",
|
||||
"1 1 6.25e-07 2.00e+01 total \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-01 total \n",
|
||||
"1 1 6.25e-01 2.00e+07 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 ((absorption / flux) / (total / flux)) 7.61e-02 6.49e-04 \n",
|
||||
|
|
@ -1042,8 +1040,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1054,8 +1052,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>((scatter / flux) / (total / flux))</td>\n",
|
||||
" <td>0.923885</td>\n",
|
||||
|
|
@ -1064,8 +1062,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>((scatter / flux) / (total / flux))</td>\n",
|
||||
" <td>0.980737</td>\n",
|
||||
|
|
@ -1076,9 +1074,9 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-07 total \n",
|
||||
"1 1 6.25e-07 2.00e+01 total \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-01 total \n",
|
||||
"1 1 6.25e-01 2.00e+07 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 ((scatter / flux) / (total / flux)) 9.24e-01 7.74e-03 \n",
|
||||
|
|
@ -1121,8 +1119,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1133,8 +1131,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
|
||||
" <td>1.0</td>\n",
|
||||
|
|
@ -1143,8 +1141,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>1</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
|
||||
" <td>1.0</td>\n",
|
||||
|
|
@ -1155,9 +1153,9 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-07 total \n",
|
||||
"1 1 6.25e-07 2.00e+01 total \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 1 0.00e+00 6.25e-01 total \n",
|
||||
"1 1 6.25e-01 2.00e+07 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 7.76e-03 \n",
|
||||
|
|
|
|||
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|
|
@ -16,6 +16,7 @@
|
|||
"outputs": [],
|
||||
"source": [
|
||||
"import glob\n",
|
||||
"\n",
|
||||
"from IPython.display import Image\n",
|
||||
"import numpy as np\n",
|
||||
"\n",
|
||||
|
|
@ -338,7 +339,7 @@
|
|||
"outputs": [
|
||||
{
|
||||
"data": {
|
||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nFrGR5QAAAABJRU5ErkJggg==\n",
|
||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nWZ8vzgAAAABJRU5ErkJggg==\n",
|
||||
"text/plain": [
|
||||
"<IPython.core.display.Image object>"
|
||||
]
|
||||
|
|
@ -386,7 +387,7 @@
|
|||
"# Create Tallies to compute microscopic multi-group cross-sections\n",
|
||||
"\n",
|
||||
"# Instantiate energy filter for multi-group cross-section Tallies\n",
|
||||
"energy_filter = openmc.EnergyFilter([0., 0.625e-6, 20.])\n",
|
||||
"energy_filter = openmc.EnergyFilter([0., 0.625, 20.0e6])\n",
|
||||
"\n",
|
||||
"# Instantiate flux Tally in moderator and fuel\n",
|
||||
"tally = openmc.Tally(name='flux')\n",
|
||||
|
|
@ -426,12 +427,12 @@
|
|||
"tallies_file.append(leak)\n",
|
||||
"\n",
|
||||
"thermal_leak = openmc.Tally(name='thermal leakage')\n",
|
||||
"thermal_leak.filters = [mesh_filter, openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"thermal_leak.filters = [mesh_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([0.625e-6, 20.])]\n",
|
||||
"fast_leak.filters = [mesh_filter, openmc.EnergyFilter([0.625, 20.0e6])]\n",
|
||||
"fast_leak.scores = ['current']\n",
|
||||
"tallies_file.append(fast_leak)"
|
||||
]
|
||||
|
|
@ -463,7 +464,7 @@
|
|||
"# Resonance Escape Probability tallies\n",
|
||||
"therm_abs_rate = openmc.Tally(name='therm. abs. rate')\n",
|
||||
"therm_abs_rate.scores = ['absorption']\n",
|
||||
"therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625])]\n",
|
||||
"tallies_file.append(therm_abs_rate)"
|
||||
]
|
||||
},
|
||||
|
|
@ -478,7 +479,7 @@
|
|||
"# Thermal Flux Utilization tallies\n",
|
||||
"fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')\n",
|
||||
"fuel_therm_abs_rate.scores = ['absorption']\n",
|
||||
"fuel_therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6]),\n",
|
||||
"fuel_therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625]),\n",
|
||||
" openmc.CellFilter([fuel_cell.id])]\n",
|
||||
"tallies_file.append(fuel_therm_abs_rate)"
|
||||
]
|
||||
|
|
@ -494,7 +495,7 @@
|
|||
"# Fast Fission Factor tallies\n",
|
||||
"therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')\n",
|
||||
"therm_fiss_rate.scores = ['nu-fission']\n",
|
||||
"therm_fiss_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"therm_fiss_rate.filters = [openmc.EnergyFilter([0., 0.625])]\n",
|
||||
"tallies_file.append(therm_fiss_rate)"
|
||||
]
|
||||
},
|
||||
|
|
@ -507,7 +508,7 @@
|
|||
"outputs": [],
|
||||
"source": [
|
||||
"# Instantiate energy filter to illustrate Tally slicing\n",
|
||||
"fine_energy_filter = openmc.EnergyFilter(np.logspace(np.log10(1e-8), np.log10(20), 10))\n",
|
||||
"fine_energy_filter = openmc.EnergyFilter(np.logspace(np.log10(1e-2), np.log10(20.0e6), 10))\n",
|
||||
"\n",
|
||||
"# Instantiate flux Tally in moderator and fuel\n",
|
||||
"tally = openmc.Tally(name='need-to-slice')\n",
|
||||
|
|
@ -578,9 +579,9 @@
|
|||
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
|
||||
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
|
||||
" Version | 0.8.0\n",
|
||||
" Git SHA1 | b02fa21928a37a2254bec13c9802ff8173b6aefd\n",
|
||||
" Date/Time | 2016-09-29 23:59:21\n",
|
||||
" MPI Processes | 1\n",
|
||||
" Git SHA1 | da5563eddb5f2c2d6b2c9839d518de40962b78f2\n",
|
||||
" Date/Time | 2016-10-31 12:54:36\n",
|
||||
" OpenMP Threads | 4\n",
|
||||
"\n",
|
||||
" ===========================================================================\n",
|
||||
" ========================> INITIALIZATION <=========================\n",
|
||||
|
|
@ -588,15 +589,15 @@
|
|||
"\n",
|
||||
" Reading settings XML file...\n",
|
||||
" Reading geometry XML file...\n",
|
||||
" Reading cross sections XML file...\n",
|
||||
" Reading materials XML file...\n",
|
||||
" Reading U235 from /home/smharper/openmc/data/nndc_hdf5/U235.h5\n",
|
||||
" Reading U238 from /home/smharper/openmc/data/nndc_hdf5/U238.h5\n",
|
||||
" Reading O16 from /home/smharper/openmc/data/nndc_hdf5/O16.h5\n",
|
||||
" Reading H1 from /home/smharper/openmc/data/nndc_hdf5/H1.h5\n",
|
||||
" Reading B10 from /home/smharper/openmc/data/nndc_hdf5/B10.h5\n",
|
||||
" Reading Zr90 from /home/smharper/openmc/data/nndc_hdf5/Zr90.h5\n",
|
||||
" Maximum neutron transport energy: 20.0000 MeV for U235\n",
|
||||
" Reading cross sections XML file...\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",
|
||||
" Maximum neutron transport energy: 2.00000E+07 eV for U235\n",
|
||||
" Reading tallies XML file...\n",
|
||||
" Building neighboring cells lists for each surface...\n",
|
||||
" Initializing source particles...\n",
|
||||
|
|
@ -636,20 +637,20 @@
|
|||
"\n",
|
||||
" =======================> TIMING STATISTICS <=======================\n",
|
||||
"\n",
|
||||
" Total time for initialization = 2.9900E-01 seconds\n",
|
||||
" Reading cross sections = 1.8000E-01 seconds\n",
|
||||
" Total time in simulation = 1.6156E+01 seconds\n",
|
||||
" Time in transport only = 1.6145E+01 seconds\n",
|
||||
" Time in inactive batches = 2.3940E+00 seconds\n",
|
||||
" Time in active batches = 1.3762E+01 seconds\n",
|
||||
" Time synchronizing fission bank = 1.0000E-03 seconds\n",
|
||||
" Sampling source sites = 1.0000E-03 seconds\n",
|
||||
" SEND/RECV source sites = 0.0000E+00 seconds\n",
|
||||
" Time accumulating tallies = 0.0000E+00 seconds\n",
|
||||
" Total time for finalization = 1.0000E-03 seconds\n",
|
||||
" Total time elapsed = 1.6476E+01 seconds\n",
|
||||
" Calculation Rate (inactive) = 5221.39 neutrons/second\n",
|
||||
" Calculation Rate (active) = 2724.89 neutrons/second\n",
|
||||
" Total time for initialization = 5.0418E-01 seconds\n",
|
||||
" Reading cross sections = 3.6765E-01 seconds\n",
|
||||
" Total time in simulation = 8.8388E+00 seconds\n",
|
||||
" Time in transport only = 8.7431E+00 seconds\n",
|
||||
" Time in inactive batches = 1.4676E+00 seconds\n",
|
||||
" Time in active batches = 7.3713E+00 seconds\n",
|
||||
" Time synchronizing fission bank = 2.2671E-03 seconds\n",
|
||||
" Sampling source sites = 1.6677E-03 seconds\n",
|
||||
" SEND/RECV source sites = 5.5964E-04 seconds\n",
|
||||
" Time accumulating tallies = 9.0487E-05 seconds\n",
|
||||
" Total time for finalization = 2.7160E-03 seconds\n",
|
||||
" Total time elapsed = 9.3633E+00 seconds\n",
|
||||
" Calculation Rate (inactive) = 8517.40 neutrons/second\n",
|
||||
" Calculation Rate (active) = 5087.33 neutrons/second\n",
|
||||
"\n",
|
||||
" ============================> RESULTS <============================\n",
|
||||
"\n",
|
||||
|
|
@ -798,8 +799,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -810,7 +811,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(absorption + current)</td>\n",
|
||||
" <td>0.695303</td>\n",
|
||||
|
|
@ -821,11 +822,11 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] nuclide score \\\n",
|
||||
"0 0.00e+00 6.25e-07 total (absorption + current) \n",
|
||||
" energy low [eV] energy high [eV] nuclide score mean \\\n",
|
||||
"0 0.00e+00 6.25e-01 total (absorption + current) 6.95e-01 \n",
|
||||
"\n",
|
||||
" mean std. dev. \n",
|
||||
"0 6.95e-01 5.09e-03 "
|
||||
" std. dev. \n",
|
||||
"0 5.09e-03 "
|
||||
]
|
||||
},
|
||||
"execution_count": 25,
|
||||
|
|
@ -866,8 +867,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -878,7 +879,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>nu-fission</td>\n",
|
||||
" <td>1.202639</td>\n",
|
||||
|
|
@ -889,8 +890,8 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] nuclide score mean std. dev.\n",
|
||||
"0 0.00e+00 6.25e-07 total nu-fission 1.20e+00 1.03e-02"
|
||||
" energy low [eV] energy high [eV] nuclide score mean std. dev.\n",
|
||||
"0 0.00e+00 6.25e-01 total nu-fission 1.20e+00 1.03e-02"
|
||||
]
|
||||
},
|
||||
"execution_count": 26,
|
||||
|
|
@ -929,8 +930,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
|
|
@ -942,7 +943,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>absorption</td>\n",
|
||||
|
|
@ -954,8 +955,8 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] cell nuclide score mean \\\n",
|
||||
"0 0.00e+00 6.25e-07 10000 total absorption 7.49e-01 \n",
|
||||
" energy low [eV] energy high [eV] cell nuclide score mean \\\n",
|
||||
"0 0.00e+00 6.25e-01 10000 total absorption 7.49e-01 \n",
|
||||
"\n",
|
||||
" std. dev. \n",
|
||||
"0 6.73e-03 "
|
||||
|
|
@ -995,8 +996,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
|
|
@ -1008,7 +1009,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(nu-fission / absorption)</td>\n",
|
||||
|
|
@ -1020,8 +1021,8 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] cell nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-07 10000 total \n",
|
||||
" energy low [eV] energy high [eV] cell nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-01 10000 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 (nu-fission / absorption) 1.66e+00 1.57e-02 "
|
||||
|
|
@ -1060,8 +1061,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1072,7 +1073,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(absorption + current)</td>\n",
|
||||
" <td>0.985102</td>\n",
|
||||
|
|
@ -1083,11 +1084,11 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] nuclide score \\\n",
|
||||
"0 0.00e+00 6.25e-07 total (absorption + current) \n",
|
||||
" energy low [eV] energy high [eV] nuclide score mean \\\n",
|
||||
"0 0.00e+00 6.25e-01 total (absorption + current) 9.85e-01 \n",
|
||||
"\n",
|
||||
" mean std. dev. \n",
|
||||
"0 9.85e-01 5.86e-03 "
|
||||
" std. dev. \n",
|
||||
"0 5.86e-03 "
|
||||
]
|
||||
},
|
||||
"execution_count": 29,
|
||||
|
|
@ -1122,8 +1123,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1134,7 +1135,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>(absorption / (absorption + current))</td>\n",
|
||||
" <td>0.997407</td>\n",
|
||||
|
|
@ -1145,8 +1146,8 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-07 total \n",
|
||||
" energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-01 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 (absorption / (absorption + current)) 9.97e-01 8.49e-03 "
|
||||
|
|
@ -1184,8 +1185,8 @@
|
|||
" <thead>\n",
|
||||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
|
|
@ -1197,7 +1198,7 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>0.0</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>total</td>\n",
|
||||
" <td>((((((absorption + current) * nu-fission) * ab...</td>\n",
|
||||
|
|
@ -1209,8 +1210,8 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" energy low [MeV] energy high [MeV] cell nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-07 10000 total \n",
|
||||
" energy low [eV] energy high [eV] cell nuclide \\\n",
|
||||
"0 0.00e+00 6.25e-01 10000 total \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 ((((((absorption + current) * nu-fission) * ab... 1.02e+00 2.06e-02 "
|
||||
|
|
@ -1267,8 +1268,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1279,8 +1280,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>(U238 / total)</td>\n",
|
||||
" <td>(nu-fission / flux)</td>\n",
|
||||
" <td>6.662479e-07</td>\n",
|
||||
|
|
@ -1289,8 +1290,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>(U238 / total)</td>\n",
|
||||
" <td>(scatter / flux)</td>\n",
|
||||
" <td>2.099897e-01</td>\n",
|
||||
|
|
@ -1299,8 +1300,8 @@
|
|||
" <tr>\n",
|
||||
" <th>2</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>(U235 / total)</td>\n",
|
||||
" <td>(nu-fission / flux)</td>\n",
|
||||
" <td>3.568130e-01</td>\n",
|
||||
|
|
@ -1309,8 +1310,8 @@
|
|||
" <tr>\n",
|
||||
" <th>3</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>(U235 / total)</td>\n",
|
||||
" <td>(scatter / flux)</td>\n",
|
||||
" <td>5.555326e-03</td>\n",
|
||||
|
|
@ -1319,8 +1320,8 @@
|
|||
" <tr>\n",
|
||||
" <th>4</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>(U238 / total)</td>\n",
|
||||
" <td>(nu-fission / flux)</td>\n",
|
||||
" <td>7.215044e-03</td>\n",
|
||||
|
|
@ -1329,8 +1330,8 @@
|
|||
" <tr>\n",
|
||||
" <th>5</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>(U238 / total)</td>\n",
|
||||
" <td>(scatter / flux)</td>\n",
|
||||
" <td>2.273966e-01</td>\n",
|
||||
|
|
@ -1339,8 +1340,8 @@
|
|||
" <tr>\n",
|
||||
" <th>6</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>(U235 / total)</td>\n",
|
||||
" <td>(nu-fission / flux)</td>\n",
|
||||
" <td>7.969615e-03</td>\n",
|
||||
|
|
@ -1349,8 +1350,8 @@
|
|||
" <tr>\n",
|
||||
" <th>7</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>(U235 / total)</td>\n",
|
||||
" <td>(scatter / flux)</td>\n",
|
||||
" <td>3.362798e-03</td>\n",
|
||||
|
|
@ -1361,15 +1362,15 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
|
||||
"0 10000 0.00e+00 6.25e-07 (U238 / total) \n",
|
||||
"1 10000 0.00e+00 6.25e-07 (U238 / total) \n",
|
||||
"2 10000 0.00e+00 6.25e-07 (U235 / total) \n",
|
||||
"3 10000 0.00e+00 6.25e-07 (U235 / total) \n",
|
||||
"4 10000 6.25e-07 2.00e+01 (U238 / total) \n",
|
||||
"5 10000 6.25e-07 2.00e+01 (U238 / total) \n",
|
||||
"6 10000 6.25e-07 2.00e+01 (U235 / total) \n",
|
||||
"7 10000 6.25e-07 2.00e+01 (U235 / total) \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide \\\n",
|
||||
"0 10000 0.00e+00 6.25e-01 (U238 / total) \n",
|
||||
"1 10000 0.00e+00 6.25e-01 (U238 / total) \n",
|
||||
"2 10000 0.00e+00 6.25e-01 (U235 / total) \n",
|
||||
"3 10000 0.00e+00 6.25e-01 (U235 / total) \n",
|
||||
"4 10000 6.25e-01 2.00e+07 (U238 / total) \n",
|
||||
"5 10000 6.25e-01 2.00e+07 (U238 / total) \n",
|
||||
"6 10000 6.25e-01 2.00e+07 (U235 / total) \n",
|
||||
"7 10000 6.25e-01 2.00e+07 (U235 / total) \n",
|
||||
"\n",
|
||||
" score mean std. dev. \n",
|
||||
"0 (nu-fission / flux) 6.66e-07 6.04e-09 \n",
|
||||
|
|
@ -1474,7 +1475,7 @@
|
|||
"source": [
|
||||
"# Show how to use Tally.get_values(...) with a CrossFilter and CrossScore\n",
|
||||
"fast_scatter_xs = fuel_xs.get_values(filters=[openmc.EnergyFilter], \n",
|
||||
" filter_bins=[((0.625e-6, 20.),)], \n",
|
||||
" filter_bins=[((0.625, 20.0e6),)], \n",
|
||||
" scores=['(scatter / flux)'])\n",
|
||||
"print(fast_scatter_xs)"
|
||||
]
|
||||
|
|
@ -1502,8 +1503,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1514,8 +1515,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>U238</td>\n",
|
||||
" <td>nu-fission</td>\n",
|
||||
" <td>0.000002</td>\n",
|
||||
|
|
@ -1524,8 +1525,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>0.000000e+00</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>0.000</td>\n",
|
||||
" <td>6.250000e-01</td>\n",
|
||||
" <td>U235</td>\n",
|
||||
" <td>nu-fission</td>\n",
|
||||
" <td>0.856784</td>\n",
|
||||
|
|
@ -1534,8 +1535,8 @@
|
|||
" <tr>\n",
|
||||
" <th>2</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>U238</td>\n",
|
||||
" <td>nu-fission</td>\n",
|
||||
" <td>0.082495</td>\n",
|
||||
|
|
@ -1544,8 +1545,8 @@
|
|||
" <tr>\n",
|
||||
" <th>3</th>\n",
|
||||
" <td>10000</td>\n",
|
||||
" <td>6.250000e-07</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>0.625</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>U235</td>\n",
|
||||
" <td>nu-fission</td>\n",
|
||||
" <td>0.091123</td>\n",
|
||||
|
|
@ -1556,11 +1557,11 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide score mean \\\n",
|
||||
"0 10000 0.00e+00 6.25e-07 U238 nu-fission 1.60e-06 \n",
|
||||
"1 10000 0.00e+00 6.25e-07 U235 nu-fission 8.57e-01 \n",
|
||||
"2 10000 6.25e-07 2.00e+01 U238 nu-fission 8.25e-02 \n",
|
||||
"3 10000 6.25e-07 2.00e+01 U235 nu-fission 9.11e-02 \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide score mean \\\n",
|
||||
"0 10000 0.00e+00 6.25e-01 U238 nu-fission 1.60e-06 \n",
|
||||
"1 10000 0.00e+00 6.25e-01 U235 nu-fission 8.57e-01 \n",
|
||||
"2 10000 6.25e-01 2.00e+07 U238 nu-fission 8.25e-02 \n",
|
||||
"3 10000 6.25e-01 2.00e+07 U235 nu-fission 9.11e-02 \n",
|
||||
"\n",
|
||||
" std. dev. \n",
|
||||
"0 1.06e-08 \n",
|
||||
|
|
@ -1596,8 +1597,8 @@
|
|||
" <tr style=\"text-align: right;\">\n",
|
||||
" <th></th>\n",
|
||||
" <th>cell</th>\n",
|
||||
" <th>energy low [MeV]</th>\n",
|
||||
" <th>energy high [MeV]</th>\n",
|
||||
" <th>energy low [eV]</th>\n",
|
||||
" <th>energy high [eV]</th>\n",
|
||||
" <th>nuclide</th>\n",
|
||||
" <th>score</th>\n",
|
||||
" <th>mean</th>\n",
|
||||
|
|
@ -1608,8 +1609,8 @@
|
|||
" <tr>\n",
|
||||
" <th>0</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.000000e-08</td>\n",
|
||||
" <td>1.080060e-07</td>\n",
|
||||
" <td>1.000000e-02</td>\n",
|
||||
" <td>1.080060e-01</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>4.547947</td>\n",
|
||||
|
|
@ -1618,8 +1619,8 @@
|
|||
" <tr>\n",
|
||||
" <th>1</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.080060e-07</td>\n",
|
||||
" <td>1.166529e-06</td>\n",
|
||||
" <td>1.080060e-01</td>\n",
|
||||
" <td>1.166529e+00</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>2.003068</td>\n",
|
||||
|
|
@ -1628,8 +1629,8 @@
|
|||
" <tr>\n",
|
||||
" <th>2</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.166529e-06</td>\n",
|
||||
" <td>1.259921e-05</td>\n",
|
||||
" <td>1.166529e+00</td>\n",
|
||||
" <td>1.259921e+01</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>1.647225</td>\n",
|
||||
|
|
@ -1638,8 +1639,8 @@
|
|||
" <tr>\n",
|
||||
" <th>3</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.259921e-05</td>\n",
|
||||
" <td>1.360790e-04</td>\n",
|
||||
" <td>1.259921e+01</td>\n",
|
||||
" <td>1.360790e+02</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>1.831367</td>\n",
|
||||
|
|
@ -1648,8 +1649,8 @@
|
|||
" <tr>\n",
|
||||
" <th>4</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.360790e-04</td>\n",
|
||||
" <td>1.469734e-03</td>\n",
|
||||
" <td>1.360790e+02</td>\n",
|
||||
" <td>1.469734e+03</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>2.039613</td>\n",
|
||||
|
|
@ -1658,8 +1659,8 @@
|
|||
" <tr>\n",
|
||||
" <th>5</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.469734e-03</td>\n",
|
||||
" <td>1.587401e-02</td>\n",
|
||||
" <td>1.469734e+03</td>\n",
|
||||
" <td>1.587401e+04</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>2.137523</td>\n",
|
||||
|
|
@ -1668,8 +1669,8 @@
|
|||
" <tr>\n",
|
||||
" <th>6</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.587401e-02</td>\n",
|
||||
" <td>1.714488e-01</td>\n",
|
||||
" <td>1.587401e+04</td>\n",
|
||||
" <td>1.714488e+05</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>2.170725</td>\n",
|
||||
|
|
@ -1678,8 +1679,8 @@
|
|||
" <tr>\n",
|
||||
" <th>7</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.714488e-01</td>\n",
|
||||
" <td>1.851749e+00</td>\n",
|
||||
" <td>1.714488e+05</td>\n",
|
||||
" <td>1.851749e+06</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>2.002724</td>\n",
|
||||
|
|
@ -1688,8 +1689,8 @@
|
|||
" <tr>\n",
|
||||
" <th>8</th>\n",
|
||||
" <td>10002</td>\n",
|
||||
" <td>1.851749e+00</td>\n",
|
||||
" <td>2.000000e+01</td>\n",
|
||||
" <td>1.851749e+06</td>\n",
|
||||
" <td>2.000000e+07</td>\n",
|
||||
" <td>H1</td>\n",
|
||||
" <td>scatter</td>\n",
|
||||
" <td>0.371624</td>\n",
|
||||
|
|
@ -1700,16 +1701,16 @@
|
|||
"</div>"
|
||||
],
|
||||
"text/plain": [
|
||||
" cell energy low [MeV] energy high [MeV] nuclide score mean \\\n",
|
||||
"0 10002 1.00e-08 1.08e-07 H1 scatter 4.55e+00 \n",
|
||||
"1 10002 1.08e-07 1.17e-06 H1 scatter 2.00e+00 \n",
|
||||
"2 10002 1.17e-06 1.26e-05 H1 scatter 1.65e+00 \n",
|
||||
"3 10002 1.26e-05 1.36e-04 H1 scatter 1.83e+00 \n",
|
||||
"4 10002 1.36e-04 1.47e-03 H1 scatter 2.04e+00 \n",
|
||||
"5 10002 1.47e-03 1.59e-02 H1 scatter 2.14e+00 \n",
|
||||
"6 10002 1.59e-02 1.71e-01 H1 scatter 2.17e+00 \n",
|
||||
"7 10002 1.71e-01 1.85e+00 H1 scatter 2.00e+00 \n",
|
||||
"8 10002 1.85e+00 2.00e+01 H1 scatter 3.72e-01 \n",
|
||||
" cell energy low [eV] energy high [eV] nuclide score mean \\\n",
|
||||
"0 10002 1.00e-02 1.08e-01 H1 scatter 4.55e+00 \n",
|
||||
"1 10002 1.08e-01 1.17e+00 H1 scatter 2.00e+00 \n",
|
||||
"2 10002 1.17e+00 1.26e+01 H1 scatter 1.65e+00 \n",
|
||||
"3 10002 1.26e+01 1.36e+02 H1 scatter 1.83e+00 \n",
|
||||
"4 10002 1.36e+02 1.47e+03 H1 scatter 2.04e+00 \n",
|
||||
"5 10002 1.47e+03 1.59e+04 H1 scatter 2.14e+00 \n",
|
||||
"6 10002 1.59e+04 1.71e+05 H1 scatter 2.17e+00 \n",
|
||||
"7 10002 1.71e+05 1.85e+06 H1 scatter 2.00e+00 \n",
|
||||
"8 10002 1.85e+06 2.00e+07 H1 scatter 3.72e-01 \n",
|
||||
"\n",
|
||||
" std. dev. \n",
|
||||
"0 2.80e-02 \n",
|
||||
|
|
@ -1735,15 +1736,6 @@
|
|||
" filters=[openmc.CellFilter], filter_bins=[(moderator_cell.id,)])\n",
|
||||
"slice_test.get_pandas_dataframe()"
|
||||
]
|
||||
},
|
||||
{
|
||||
"cell_type": "code",
|
||||
"execution_count": null,
|
||||
"metadata": {
|
||||
"collapsed": true
|
||||
},
|
||||
"outputs": [],
|
||||
"source": []
|
||||
}
|
||||
],
|
||||
"metadata": {
|
||||
|
|
|
|||
|
|
@ -1520,7 +1520,7 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
|
||||
.. code-block:: xml
|
||||
|
||||
<filter type="energy" bins="0.0 1.0 20.0" />
|
||||
<filter type="energy" bins="0.0 1.0e6 20.0e6" />
|
||||
|
||||
then two energy bins will be created, one with energies between 0 and
|
||||
1 MeV and the other with energies between 1 and 20 MeV.
|
||||
|
|
@ -1535,7 +1535,7 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
|
||||
.. code-block:: xml
|
||||
|
||||
<filter type="energyout" bins="0.0 1.0 20.0" />
|
||||
<filter type="energyout" bins="0.0 1.0e6 20.0e6" />
|
||||
|
||||
then two post-collision energy bins will be created, one with
|
||||
energies between 0 and 1 MeV and the other with energies between
|
||||
|
|
@ -1854,7 +1854,7 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
| |particles. The neutrino energy does not contribute |
|
||||
| |to this response. The prompt and delayed |
|
||||
| |:math:`\gamma`-rays are assumed to deposit their |
|
||||
| |energy locally. Units are MeV per source particle. |
|
||||
| |energy locally. Units are eV per source particle. |
|
||||
+----------------------+---------------------------------------------------+
|
||||
|fission-q-prompt |The prompt fission energy production rate. This |
|
||||
| |energy comes in the form of fission fragment |
|
||||
|
|
@ -1863,7 +1863,7 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
| |incident energy and it requires that the nuclear |
|
||||
| |data library contains the optional fission energy |
|
||||
| |release data. Energy is assumed to be deposited |
|
||||
| |locally. Units are MeV per source particle. |
|
||||
| |locally. Units are eV per source particle. |
|
||||
+----------------------+---------------------------------------------------+
|
||||
|fission-q-recoverable |The recoverable fission energy production rate. |
|
||||
| |This energy comes in the form of fission fragment |
|
||||
|
|
@ -1874,7 +1874,7 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
| |incident neutron energy and it requires that the |
|
||||
| |nuclear data library contains the optional fission |
|
||||
| |energy release data. Energy is assumed to be |
|
||||
| |deposited locally. Units are MeV per source |
|
||||
| |deposited locally. Units are eV per source |
|
||||
| |paticle. |
|
||||
+----------------------+---------------------------------------------------+
|
||||
|decay-rate |The delayed-nu-fission-weighted decay rate where |
|
||||
|
|
@ -2296,7 +2296,7 @@ attributes/sub-elements:
|
|||
The width of mesh cells in each direction.
|
||||
|
||||
:energy:
|
||||
Energy bins [in MeV], listed in ascending order (e.g. 0.0 0.625e-7 20.0)
|
||||
Energy bins [in eV], listed in ascending order (e.g. 0.0 0.625 20.0e6)
|
||||
for CMFD tallies and acceleration. If no energy bins are listed, OpenMC
|
||||
automatically assumes a one energy group calculation over the entire
|
||||
energy range.
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue