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51 // Copyright (c) 2006 The Regents of the University of California.
52 // All rights reserved.
53 // UCRL-CODE-224807
54 //
55 //
56 //
57
58 #include "G4fissionEvent.hh"
59
60 #define nSPfissIso 8
61 #define nSPfissn 11
62
63 G4int G4fissionEvent::G4SmpSpNuDistData(G4int isotope, G4int Cf252option) {
64
65 /*
66 Description
67 Sample Number of Neutrons from spontaneous fission
68 (a) from the neutron multiplicity data for
69 U-238, Pu-238, Pu-240, Pu-242, Cm-242, Cm-244
70 using Holden and Zucker's tabulated data
71 Cf-252 using either Spencer's tabulated data or
72 Boldeman's data
73 (b) from Terrell's approximation using nubar for
74 Th-232,
75 U-232, U-233, U-234, U-235, U-236,
76 Np-237,
77 Pu-239, Pu-241,
78 Am-241,
79 Bk-249
80 using Ensslin's data.
81 */
82
83 /*
84 Input
85 iso - isotope
86 Cf252option - 0 to use Spencer's tabulated data
87 1 to use Boldeman's data
88 Output
89 G4SmpSpNuDistData - sampled multiplicity
90 -1 is the isotope has
91 no multiplicity data,
92 nor any nubar data
93 */
94
95 G4int i, index;
96 G4double sum, nubar;
97 G4double r;
98
99 static G4double sfnu [nSPfissIso][nSPfissn] = {
100 {0.0481677,0.2485215,0.4253044,0.2284094,0.0423438,0.0072533,
101 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000},
102
103 {0.0631852,0.2319644,0.3333230,0.2528207,0.0986461,0.0180199,
104 0.0020407,0.0000000,0.0000000,0.0000000,0.0000000},
105
106 {0.0679423,0.2293159,0.3341228,0.2475507,0.0996922,0.0182398,
107 0.0031364,0.0000000,0.0000000,0.0000000,0.0000000},
108
109 {0.0212550,0.1467407,0.3267531,0.3268277,0.1375090,0.0373815,
110 0.0025912,0.0007551,0.0001867,0.0000000,0.0000000},
111
112 {0.0150050,0.1161725,0.2998427,0.3331614,0.1837748,0.0429780,
113 0.0087914,0.0002744,0.0000000,0.0000000,0.0000000},
114
115 {0.0540647,0.2053880,0.3802279,0.2248483,0.1078646,0.0276366,
116 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000},
117
118 {0.0021100,0.0246700,0.1229000,0.2714400,0.3076300,0.1877000,
119 0.0677000,0.0140600,0.0016700,0.0001000,0.0000000},
120
121 {0.0020900,0.0262100,0.1262000,0.2752000,0.3018000,0.1846000,
122 0.0668000,0.0150000,0.0021000,0.0000000,0.0000000} };
123
124 /*
125 sample the spontaneous fission neutron number distribution
126 */
127 index = -1;
128
129 if (isotope == 92238) index = 0;
130 else if (isotope == 94240) index = 1;
131 else if (isotope == 94242) index = 2;
132 else if (isotope == 96242) index = 3;
133 else if (isotope == 96244) index = 4;
134 else if (isotope == 94238) index = 5;
135 else if (isotope == 98252 && Cf252option == 0) index = 6;
136 else if (isotope == 98252 && Cf252option == 1) index = 7;
137
138 if (index != -1) {
139 r=fisslibrng();
140
141 sum = 0.;
142 for (i = 0; i < nSPfissn-1; i++) {
143 sum = sum + sfnu[index][i];
144 if (r <= sum || sfnu[index][i+1] == 0.) return i;
145 }
146 //
147 // Fall through
148 //
149 G4cout << " Random number out of range in SmpSpNuDistData " << G4endl;
150 return -1;
151
152 } else {
153 // There is no full multiplicity distribution data available
154 // for that isotope, let's try to find a nubar for it in
155 // N. Ensslin, et.al., "Application Guide to Neutron
156 // Multiplicity Counting," LA-13422-M (November 1998)
157 // and use Terrell's approximation
158 nubar = G4SmpSpNubarData(isotope);
159 if (nubar != -1.) {
160 return (G4int) G4SmpTerrell(nubar);
161 } else {
162 // There is no nubar information for that isotope, return -1,
163 // meaning no data available for that isotope
164 return -1;
165 }
166 }
167 }
168