Geant4 10.7.0
Toolkit for the simulation of the passage of particles through matter
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G4WattFissionSpectrumValues.hh
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26/*
27 * File: G4WattFissionSpectrumValues.hh
28 * Author: B. Wendt ([email protected])
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
51/** WattSpectrumConstants contains constants and other variables for use in
52 * sampling the Watt fission spectrum.
53 */
55{
56 /** Isotope code in ZZZAAA format for which the Watt fission
57 * spectrum is being sampled
58 */
60 /** Fission cause for which the Watt fission spectrum is being
61 * sampled
62 */
64 /** Energy, if any, of the incident particle that cause the fission */
66
67 /** Sampling constant. Calculated as:
68 * \f[
69 * L = \frac{[K + (K^2 - 1)^\frac{1}{2}]}{a}
70 * \f]
71 * \f[
72 * K = 1 + \frac{b}{8a}
73 * \f]
74 */
76 /** Sampling constant. Calculated as:
77 * \f[
78 * M = a*L-1
79 * \f]
80 */
82 /** Sampling constant taken from the data tables. */
84};
85
86/** These are the energy values in MeV for the neutron induced Watt fission
87 * spectrum constants.
88 */
89static const G4double IncidentEnergyBins[] =
90{
91 G4FFGDefaultValues::ThermalNeutronEnergy,
92 1.0 * CLHEP::MeV,
93 14.0 * CLHEP::MeV,
94 -1 // End of array
95};
96
97/** Watt fission spectrum constants for neutron induced fission.
98 * \n <b> Constants </b>
99 * \n Column 1: 'a' value
100 * \n Column 2: 'b' value
101 *
102 * \n <b> Incident Neutron Energies </b>
103 * \n Row 1: Thermal (~0.025 eV)
104 * \n Row 2: 1 MeV
105 * \n Row 3: 14 MeV
106 */
107static 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
138/** This table provides the indexing for NeutronInducedWattConstants_. The
139 * index of an isotope in this table is the index for the Watt fission spectrum
140 * constants in NeutronInducedWattConstants_. The isotopes are listed in ZZZAAA
141 * format.
142 */
143static const G4int NeutronInducedWattIsotopesIndex[] =
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
159/** Watt fission spectrum constants for spontaneous fission.
160 * \n Column 1: 'a' value
161 * \n Column 2: 'b' value
162 */
163static const G4double SpontaneousWattConstants[][2] =
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
182/** This table provides the indexing for SpontaneousWattConstants_. The index of
183 * an isotope in this table is the index for the Watt fission spectrum constants
184 * in SpontaneousWattConstants_. The isotopes are listed in ZZZAAA format.
185 */
186static const G4int SpontaneousWattIsotopesIndex[] =
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
double G4double
Definition: G4Types.hh:83
int G4int
Definition: G4Types.hh:85
G4FFGEnumerations::FissionCause Cause