source: trunk/source/processes/hadronic/models/lll_fission/src/G4SmpSpNuDistData.cc @ 962

Last change on this file since 962 was 819, checked in by garnier, 16 years ago

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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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