Geant4  10.02.p01
G4WattFissionSpectrumValues.hh
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26 /*
27  * File: G4WattFissionSpectrumValues.hh
28  * Author: B. Wendt (wendbryc@isu.edu)
29  *
30  * Created on July 11, 2011, 11:32 AM
31  */
32 
33 /* * * * * * * * * * * * * * * * References * * * * * * * * * * * * * * * *
34  * *
35  * 1. MCNP - A General Monte carlo N-Particle Transport Code, Version 5, *
36  * X-5 Monte Carlo Team, Volume I: Overview and Theory, April, 2005 *
37  * *
38  * * * * * * * * * * * * * * * * References * * * * * * * * * * * * * * * */
39 
40 #ifndef G4WATTFISSIONSPECTRUMVALUES_HH
41 #define G4WATTFISSIONSPECTRUMVALUES_HH
42 
43 #include "globals.hh"
44 
45 #include "G4FFGDefaultValues.hh"
46 #include "G4FFGEnumerations.hh"
47 
48 // TODO Migrate to existing neutron_hp watt constants in G4NeutronHPWattSpectrum.hh
49 // and then remove this file from the repo and sources.cmake
50 
55 {
66 
84 };
85 
89 static const G4double IncidentEnergyBins[] =
90 {
92  1.0 * MeV,
93  14.0 * MeV,
94  -1 // End of array
95 };
96 
107 static const G4double NeutronInducedWattConstants[][3][2] =
108 {
109 // Default
110  { {0.95, 2.7},
111  {1.0, 2.5},
112  {1.05, 2.4}, },
113 // Thorium
114  // 90232
115  { {1.0888, 1.6871},
116  {1.1096, 1.6316},
117  {1.1700, 1.4610}, },
118 // Uranium
119  // 92233
120  { {0.977, 2.546},
121  {0.977, 2.249},
122  {1.0036, 2.6377}, },
123  // 92235
124  { {0.988, 2.249},
125  {0.988, 2.249},
126  {1.028, 2.084}, },
127  // 92238
128  { {0.88111, 3.4005},
129  {0.89506, 3.2953},
130  {0.96534, 2.8330}, },
131 // Plutonium
132  // 94239
133  { {0.966, 2.842},
134  {0.966, 2.842},
135  {1.055, 2.383}, }
136 };
137 
144 {
145 // Default
146  0,
147 // Thorium
148  90232,
149 // Uranium
150  92233,
151  92235,
152  92238,
153 // Plutonium
154  94239,
155 // End of array
156  -1
157 };
158 
164 {
165 // Default
166  {0.8, 4.0},
167 // Plutonium
168  // 94240
169  {0.799, 4.903},
170  // 94242
171  {0.833668, 4.431658},
172 // Curium
173  // 96242
174  {0.891, 4.046},
175  // 96244
176  {0.906, 3.848},
177 // Californium
178  // 98252
179  {1.025, 2.926}
180 };
181 
187 {
188 // Default
189  0,
190 // Plutonium
191  94240,
192  94242,
193 // Curium
194  96242,
195  96244,
196 // Californium
197  98252,
198 // End of array
199  -1
200 };
201 
202 #endif /* G4WATTFISSIONSPECTRUMVALUES_HH */
203 
static const double MeV
Definition: G4SIunits.hh:211
static const G4double NeutronInducedWattConstants[][3][2]
Watt fission spectrum constants for neutron induced fission.
WattSpectrumConstants contains constants and other variables for use in sampling the Watt fission spe...
G4double Energy
Energy, if any, of the incident particle that cause the fission.
static const G4double SpontaneousWattConstants[][2]
Watt fission spectrum constants for spontaneous fission.
G4FFGEnumerations::FissionCause Cause
Fission cause for which the Watt fission spectrum is being sampled.
int G4int
Definition: G4Types.hh:78
FissionCause
Causes of fission.
G4double M
Sampling constant.
G4int Product
Isotope code in ZZZAAA format for which the Watt fission spectrum is being sampled.
static const G4int SpontaneousWattIsotopesIndex[]
This table provides the indexing for SpontaneousWattConstants_.
G4double B
Sampling constant taken from the data tables.
static const G4int NeutronInducedWattIsotopesIndex[]
This table provides the indexing for NeutronInducedWattConstants_.
G4double L
Sampling constant.
double G4double
Definition: G4Types.hh:76
static const G4double IncidentEnergyBins[]
These are the energy values in MeV for the neutron induced Watt fission spectrum constants.
static const G4double ThermalNeutronEnergy
The energy of thermal neutrons.