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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 "G4FFGDefaultValues.hh"
44 #include "G4FFGEnumerations.hh"
45 #include "globals.hh"
46
47 // TODO Migrate to existing neutron_hp watt constants in G4NeutronHPWattSpectrum.hh
48 // and then remove this file from the repo and sources.cmake
49
50 /** WattSpectrumConstants contains constants and other variables for use in
51 * sampling the Watt fission spectrum.
52 */
53 struct WattSpectrumConstants
54 {
55 /** Isotope code in ZZZAAA format for which the Watt fission
56 * spectrum is being sampled
57 */
58 G4int Product;
59 /** Fission cause for which the Watt fission spectrum is being
60 * sampled
61 */
62 G4FFGEnumerations::FissionCause Cause;
63 /** Energy, if any, of the incident particle that cause the fission */
64 G4double Energy;
65
66 /** Sampling constant. Calculated as:
67 * \f[
68 * L = \frac{[K + (K^2 - 1)^\frac{1}{2}]}{a}
69 * \f]
70 * \f[
71 * K = 1 + \frac{b}{8a}
72 * \f]
73 */
74 G4double L;
75 /** Sampling constant. Calculated as:
76 * \f[
77 * M = a*L-1
78 * \f]
79 */
80 G4double M;
81 /** Sampling constant taken from the data tables. */
82 G4double B;
83 };
84
85 /** These are the energy values in MeV for the neutron induced Watt fission
86 * spectrum constants.
87 */
88 static const G4double IncidentEnergyBins[] = {
89 G4FFGDefaultValues::ThermalNeutronEnergy, 1.0 * CLHEP::MeV, 14.0 * CLHEP::MeV,
90 -1 // End of array
91 };
92
93 /** Watt fission spectrum constants for neutron induced fission.
94 * \n <b> Constants </b>
95 * \n Column 1: 'a' value
96 * \n Column 2: 'b' value
97 *
98 * \n <b> Incident Neutron Energies </b>
99 * \n Row 1: Thermal (~0.025 eV)
100 * \n Row 2: 1 MeV
101 * \n Row 3: 14 MeV
102 */
103 static const G4double NeutronInducedWattConstants[][3][2] = {
104 // Default
105 {
106 {0.95, 2.7},
107 {1.0, 2.5},
108 {1.05, 2.4},
109 },
110 // Thorium
111 // 90232
112 {
113 {1.0888, 1.6871},
114 {1.1096, 1.6316},
115 {1.1700, 1.4610},
116 },
117 // Uranium
118 // 92233
119 {
120 {0.977, 2.546},
121 {0.977, 2.249},
122 {1.0036, 2.6377},
123 },
124 // 92235
125 {
126 {0.988, 2.249},
127 {0.988, 2.249},
128 {1.028, 2.084},
129 },
130 // 92238
131 {
132 {0.88111, 3.4005},
133 {0.89506, 3.2953},
134 {0.96534, 2.8330},
135 },
136 // Plutonium
137 // 94239
138 {
139 {0.966, 2.842},
140 {0.966, 2.842},
141 {1.055, 2.383},
142 }};
143
144 /** This table provides the indexing for NeutronInducedWattConstants_. The
145 * index of an isotope in this table is the index for the Watt fission spectrum
146 * constants in NeutronInducedWattConstants_. The isotopes are listed in ZZZAAA
147 * format.
148 */
149 static const G4int NeutronInducedWattIsotopesIndex[] = {
150 // Default
151 0,
152 // Thorium
153 90232,
154 // Uranium
155 92233, 92235, 92238,
156 // Plutonium
157 94239,
158 // End of array
159 -1};
160
161 /** Watt fission spectrum constants for spontaneous fission.
162 * \n Column 1: 'a' value
163 * \n Column 2: 'b' value
164 */
165 static const G4double SpontaneousWattConstants[][2] = {
166 // Default
167 {0.8, 4.0},
168 // Plutonium
169 // 94240
170 {0.799, 4.903},
171 // 94242
172 {0.833668, 4.431658},
173 // Curium
174 // 96242
175 {0.891, 4.046},
176 // 96244
177 {0.906, 3.848},
178 // Californium
179 // 98252
180 {1.025, 2.926}};
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 */
186 static const G4int SpontaneousWattIsotopesIndex[] = {
187 // Default
188 0,
189 // Plutonium
190 94240, 94242,
191 // Curium
192 96242, 96244,
193 // Californium
194 98252,
195 // End of array
196 -1};
197
198 #endif /* G4WATTFISSIONSPECTRUMVALUES_HH */
199