Geant4_10
G4SmpSpNuDistData.cc
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56 // $Id: G4SmpSpNuDistData.cc 68799 2013-04-05 13:29:46Z gcosmo $
57 //
58 
59 #include "G4fissionEvent.hh"
60 
61 #define nSPfissIso 8
62 #define nSPfissn 11
63 
64 G4int 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-1; 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 }
#define nSPfissIso
Int_t index
Definition: macro.C:9
int G4int
Definition: G4Types.hh:78
#define nSPfissn
G4GLOB_DLL std::ostream G4cout
jump r
Definition: plot.C:36
#define G4endl
Definition: G4ios.hh:61
double G4double
Definition: G4Types.hh:76