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0001 //
0002 // ********************************************************************
0003 // * License and Disclaimer                                           *
0004 // *                                                                  *
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0006 // * the Geant4 Collaboration.  It is provided  under  the terms  and *
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0015 // * use.  Please see the license in the file  LICENSE  and URL above *
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0017 // *                                                                  *
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0019 // * technical work of the GEANT4 collaboration.                      *
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0021 // * any work based  on the software)  you  agree  to acknowledge its *
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0024 // ********************************************************************
0025 //
0026 /*
0027  * File:   G4WattFissionSpectrumValues.hh
0028  * Author: B. Wendt (wendbryc@isu.edu)
0029  *
0030  * Created on July 11, 2011, 11:32 AM
0031  */
0032 
0033 /* * * * * * * * * * * * * * * *   References   * * * * * * * * * * * * * * * *
0034  *                                                                            *
0035  *  1.  MCNP - A General Monte carlo N-Particle Transport Code, Version 5,    *
0036  *      X-5 Monte Carlo Team, Volume I: Overview and Theory, April, 2005      *
0037  *                                                                            *
0038  * * * * * * * * * * * * * * * *   References   * * * * * * * * * * * * * * * */
0039 
0040 #ifndef G4WATTFISSIONSPECTRUMVALUES_HH
0041 #define G4WATTFISSIONSPECTRUMVALUES_HH
0042 
0043 #include "G4FFGDefaultValues.hh"
0044 #include "G4FFGEnumerations.hh"
0045 #include "globals.hh"
0046 
0047 // TODO Migrate to existing neutron_hp watt constants in G4NeutronHPWattSpectrum.hh
0048 //      and then remove this file from the repo and sources.cmake
0049 
0050 /** WattSpectrumConstants contains constants and other variables for use in
0051  *  sampling the Watt fission spectrum.
0052  */
0053 struct WattSpectrumConstants
0054 {
0055     /** Isotope code in ZZZAAA format for which the Watt fission
0056      *  spectrum is being sampled
0057      */
0058     G4int Product;
0059     /** Fission cause for which the Watt fission spectrum is being
0060      * sampled
0061      */
0062     G4FFGEnumerations::FissionCause Cause;
0063     /** Energy, if any, of the incident particle that cause the fission */
0064     G4double Energy;
0065 
0066     /** Sampling constant. Calculated as:
0067      * \f[
0068      *  L = \frac{[K + (K^2 - 1)^\frac{1}{2}]}{a}
0069      * \f]
0070      * \f[
0071      * K = 1 + \frac{b}{8a}
0072      * \f]
0073      */
0074     G4double L;
0075     /** Sampling constant. Calculated as:
0076      * \f[
0077      * M = a*L-1
0078      * \f]
0079      */
0080     G4double M;
0081     /** Sampling constant taken from the data tables. */
0082     G4double B;
0083 };
0084 
0085 /** These are the energy values in MeV for the neutron induced Watt fission
0086  *  spectrum constants.
0087  */
0088 static const G4double IncidentEnergyBins[] = {
0089   G4FFGDefaultValues::ThermalNeutronEnergy, 1.0 * CLHEP::MeV, 14.0 * CLHEP::MeV,
0090   -1  // End of array
0091 };
0092 
0093 /** Watt fission spectrum constants for neutron induced fission.
0094  *  \n <b> Constants </b>
0095  *  \n Column 1: 'a' value
0096  *  \n Column 2: 'b' value
0097  *
0098  *  \n <b> Incident Neutron Energies </b>
0099  *  \n Row 1: Thermal (~0.025 eV)
0100  *  \n Row 2: 1 MeV
0101  *  \n Row 3: 14 MeV
0102  */
0103 static const G4double NeutronInducedWattConstants[][3][2] = {
0104   // Default
0105   {
0106     {0.95, 2.7},
0107     {1.0, 2.5},
0108     {1.05, 2.4},
0109   },
0110   // Thorium
0111   // 90232
0112   {
0113     {1.0888, 1.6871},
0114     {1.1096, 1.6316},
0115     {1.1700, 1.4610},
0116   },
0117   // Uranium
0118   // 92233
0119   {
0120     {0.977, 2.546},
0121     {0.977, 2.249},
0122     {1.0036, 2.6377},
0123   },
0124   // 92235
0125   {
0126     {0.988, 2.249},
0127     {0.988, 2.249},
0128     {1.028, 2.084},
0129   },
0130   // 92238
0131   {
0132     {0.88111, 3.4005},
0133     {0.89506, 3.2953},
0134     {0.96534, 2.8330},
0135   },
0136   // Plutonium
0137   // 94239
0138   {
0139     {0.966, 2.842},
0140     {0.966, 2.842},
0141     {1.055, 2.383},
0142   }};
0143 
0144 /** This table provides the indexing for NeutronInducedWattConstants_. The
0145  *  index of an isotope in this table is the index for the Watt fission spectrum
0146  *  constants in NeutronInducedWattConstants_. The isotopes are listed in ZZZAAA
0147  *  format.
0148  */
0149 static const G4int NeutronInducedWattIsotopesIndex[] = {
0150   // Default
0151   0,
0152   // Thorium
0153   90232,
0154   // Uranium
0155   92233, 92235, 92238,
0156   // Plutonium
0157   94239,
0158   // End of array
0159   -1};
0160 
0161 /** Watt fission spectrum constants for spontaneous fission.
0162  *  \n Column 1: 'a' value
0163  *  \n Column 2: 'b' value
0164  */
0165 static const G4double SpontaneousWattConstants[][2] = {
0166   // Default
0167   {0.8, 4.0},
0168   // Plutonium
0169   // 94240
0170   {0.799, 4.903},
0171   // 94242
0172   {0.833668, 4.431658},
0173   // Curium
0174   // 96242
0175   {0.891, 4.046},
0176   // 96244
0177   {0.906, 3.848},
0178   // Californium
0179   // 98252
0180   {1.025, 2.926}};
0181 
0182 /** This table provides the indexing for SpontaneousWattConstants_. The index of
0183  *  an isotope in this table is the index for the Watt fission spectrum constants
0184  *  in SpontaneousWattConstants_. The isotopes are listed in ZZZAAA format.
0185  */
0186 static const G4int SpontaneousWattIsotopesIndex[] = {
0187   // Default
0188   0,
0189   // Plutonium
0190   94240, 94242,
0191   // Curium
0192   96242, 96244,
0193   // Californium
0194   98252,
0195   // End of array
0196   -1};
0197 
0198 #endif /* G4WATTFISSIONSPECTRUMVALUES_HH */