source: trunk/source/processes/hadronic/models/lll_fission/src/G4SmpSpNuDistData.cc@ 1036

Last change on this file since 1036 was 819, checked in by garnier, 17 years ago

import all except CVS
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53// UCRL-CODE-224807
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56// $Id: G4SmpSpNuDistData.cc,v 1.2 2007/05/30 19:01:32 dennis Exp $
57//
58
59#include "G4fissionEvent.hh"
60
61#define nSPfissIso 8
62#define nSPfissn 11
63
64G4int G4fissionEvent::G4SmpSpNuDistData(G4int isotope, G4int Cf252option) {
65
66/*
67 Description
68 Sample Number of Neutrons from spontaneous fission
69 (a) from the neutron multiplicity data for
70 U-238, Pu-238, Pu-240, Pu-242, Cm-242, Cm-244
71 using Holden and Zucker's tabulated data
72 Cf-252 using either Spencer's tabulated data or
73 Boldeman's data
74 (b) from Terrell's approximation using nubar for
75 Th-232,
76 U-232, U-233, U-234, U-235, U-236,
77 Np-237,
78 Pu-239, Pu-241,
79 Am-241,
80 Bk-249
81 using Ensslin's data.
82*/
83
84/*
85 Input
86 iso - isotope
87 Cf252option - 0 to use Spencer's tabulated data
88 1 to use Boldeman's data
89 Output
90 G4SmpSpNuDistData - sampled multiplicity
91 -1 is the isotope has
92 no multiplicity data,
93 nor any nubar data
94*/
95
96 G4int i, index;
97 G4double sum, nubar;
98 G4double r;
99
100 static G4double sfnu [nSPfissIso][nSPfissn] = {
101 {0.0481677,0.2485215,0.4253044,0.2284094,0.0423438,0.0072533,
102 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000},
103
104 {0.0631852,0.2319644,0.3333230,0.2528207,0.0986461,0.0180199,
105 0.0020407,0.0000000,0.0000000,0.0000000,0.0000000},
106
107 {0.0679423,0.2293159,0.3341228,0.2475507,0.0996922,0.0182398,
108 0.0031364,0.0000000,0.0000000,0.0000000,0.0000000},
109
110 {0.0212550,0.1467407,0.3267531,0.3268277,0.1375090,0.0373815,
111 0.0025912,0.0007551,0.0001867,0.0000000,0.0000000},
112
113 {0.0150050,0.1161725,0.2998427,0.3331614,0.1837748,0.0429780,
114 0.0087914,0.0002744,0.0000000,0.0000000,0.0000000},
115
116 {0.0540647,0.2053880,0.3802279,0.2248483,0.1078646,0.0276366,
117 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000},
118
119 {0.0021100,0.0246700,0.1229000,0.2714400,0.3076300,0.1877000,
120 0.0677000,0.0140600,0.0016700,0.0001000,0.0000000},
121
122 {0.0020900,0.0262100,0.1262000,0.2752000,0.3018000,0.1846000,
123 0.0668000,0.0150000,0.0021000,0.0000000,0.0000000} };
124
125/*
126 sample the spontaneous fission neutron number distribution
127*/
128 index = -1;
129
130 if (isotope == 92238) index = 0;
131 else if (isotope == 94240) index = 1;
132 else if (isotope == 94242) index = 2;
133 else if (isotope == 96242) index = 3;
134 else if (isotope == 96244) index = 4;
135 else if (isotope == 94238) index = 5;
136 else if (isotope == 98252 && Cf252option == 0) index = 6;
137 else if (isotope == 98252 && Cf252option == 1) index = 7;
138
139 if (index != -1) {
140 r=fisslibrng();
141
142 sum=0.;
143 for(i=0; i<nSPfissn; i++) {
144 sum=sum+sfnu[index][i];
145 if (r <= sum || sfnu[index][i+1] == 0.) return i;
146 }
147 //
148 // Fall through
149 //
150 G4cout << " Random number out of range in SmpSpNuDistData " << G4endl;
151 return -1;
152
153 } else {
154// There is no full multiplicity distribution data available
155// for that isotope, let's try to find a nubar for it in
156// N. Ensslin, et.al., "Application Guide to Neutron
157// Multiplicity Counting," LA-13422-M (November 1998)
158// and use Terrell's approximation
159 nubar = G4SmpSpNubarData(isotope);
160 if (nubar != -1.) {
161 return (G4int) G4SmpTerrell(nubar);
162 } else {
163// There is no nubar information for that isotope, return -1,
164// meaning no data available for that isotope
165 return -1;
166 }
167 }
168}
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