openmc.data
– Nuclear Data Interface¶
Core Classes¶
openmc.data.IncidentNeutron |
Continuous-energy neutron interaction data. |
openmc.data.Reaction |
A nuclear reaction |
openmc.data.Product |
Secondary particle emitted in a nuclear reaction |
openmc.data.Tabulated1D |
A one-dimensional tabulated function. |
openmc.data.FissionEnergyRelease |
Energy relased by fission reactions. |
openmc.data.ThermalScattering |
A ThermalScattering object contains thermal scattering data as represented by an S(alpha, beta) table. |
openmc.data.CoherentElastic |
Coherent elastic scattering data from a crystalline material |
openmc.data.FissionEnergyRelease |
Energy relased by fission reactions. |
openmc.data.DataLibrary |
Collection of cross section data libraries. |
openmc.data.Decay |
Radioactive decay data. |
openmc.data.FissionProductYields |
Independent and cumulative fission product yields. |
openmc.data.WindowedMultipole |
Resonant cross sections represented in the windowed multipole format. |
Core Functions¶
openmc.data.atomic_mass |
Return atomic mass of isotope in atomic mass units. |
openmc.data.linearize |
Return a tabulated representation of a function of one variable. |
openmc.data.thin |
Check for (x,y) points that can be removed. |
openmc.data.write_compact_458_library |
Read ENDF files, strip the MF=1 MT=458 data and write to small HDF5. |
Angle-Energy Distributions¶
openmc.data.AngleEnergy |
Distribution in angle and energy of a secondary particle. |
openmc.data.KalbachMann |
Kalbach-Mann distribution |
openmc.data.CorrelatedAngleEnergy |
Correlated angle-energy distribution |
openmc.data.UncorrelatedAngleEnergy |
Uncorrelated angle-energy distribution |
openmc.data.NBodyPhaseSpace |
N-body phase space distribution |
openmc.data.LaboratoryAngleEnergy |
Laboratory angle-energy distribution |
openmc.data.AngleDistribution |
Angle distribution as a function of incoming energy |
openmc.data.EnergyDistribution |
Abstract superclass for all energy distributions. |
openmc.data.ArbitraryTabulated |
Arbitrary tabulated function given in ENDF MF=5, LF=1 represented as |
openmc.data.GeneralEvaporation |
General evaporation spectrum given in ENDF MF=5, LF=5 represented as |
openmc.data.MaxwellEnergy |
Simple Maxwellian fission spectrum represented as |
openmc.data.Evaporation |
Evaporation spectrum represented as |
openmc.data.WattEnergy |
Energy-dependent Watt spectrum represented as |
openmc.data.MadlandNix |
Energy-dependent fission neutron spectrum (Madland and Nix) given in |
openmc.data.DiscretePhoton |
Discrete photon energy distribution |
openmc.data.LevelInelastic |
Level inelastic scattering |
openmc.data.ContinuousTabular |
Continuous tabular distribution |
Resonance Data¶
openmc.data.Resonances |
Resolved and unresolved resonance data |
openmc.data.ResonanceRange |
Resolved resonance range |
openmc.data.SingleLevelBreitWigner |
Single-level Breit-Wigner resolved resonance formalism data. |
openmc.data.MultiLevelBreitWigner |
Multi-level Breit-Wigner resolved resonance formalism data. |
openmc.data.ReichMoore |
Reich-Moore resolved resonance formalism data. |
openmc.data.RMatrixLimited |
R-matrix limited resolved resonance formalism data. |
openmc.data.ParticlePair |
|
openmc.data.SpinGroup |
Resonance spin group |
openmc.data.Unresolved |
Unresolved resonance parameters as identified by LRU=2 in MF=2. |
ACE Format¶
Classes¶
openmc.data.ace.Library |
A Library objects represents an ACE-formatted file which may contain multiple tables with data. |
openmc.data.ace.Table |
ACE cross section table |
Functions¶
openmc.data.ace.ascii_to_binary |
Convert an ACE file in ASCII format (type 1) to binary format (type 2). |
ENDF Format¶
Classes¶
openmc.data.endf.Evaluation |
ENDF material evaluation with multiple files/sections |
Functions¶
openmc.data.endf.float_endf |
Convert string of floating point number in ENDF to float. |
openmc.data.endf.get_cont_record |
Return data from a CONT record in an ENDF-6 file. |
openmc.data.endf.get_evaluations |
Return a list of all evaluations within an ENDF file. |
openmc.data.endf.get_head_record |
Return data from a HEAD record in an ENDF-6 file. |
openmc.data.endf.get_tab1_record |
Return data from a TAB1 record in an ENDF-6 file. |
openmc.data.endf.get_tab2_record |
|
openmc.data.endf.get_text_record |
Return data from a TEXT record in an ENDF-6 file. |
NJOY Interface¶
openmc.data.njoy.run |
Run NJOY with given commands |
openmc.data.njoy.make_pendf |
Generate ACE file from an ENDF file |
openmc.data.njoy.make_ace |
Generate incident neutron ACE file from an ENDF file |
openmc.data.njoy.make_ace_thermal |
Generate thermal scattering ACE file from ENDF files |