source: trunk/source/processes/hadronic/models/neutron_hp/src/G4NeutronHPFission.cc@ 1199

Last change on this file since 1199 was 819, checked in by garnier, 17 years ago

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1//
2// ********************************************************************
3// * License and Disclaimer *
4// * *
5// * The Geant4 software is copyright of the Copyright Holders of *
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15// * use. Please see the license in the file LICENSE and URL above *
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17// * *
18// * This code implementation is the result of the scientific and *
19// * technical work of the GEANT4 collaboration. *
20// * By using, copying, modifying or distributing the software (or *
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24// ********************************************************************
25//
26// neutron_hp -- source file
27// J.P. Wellisch, Nov-1996
28// A prototype of the low energy neutron transport model.
29//
30// 070523 bug fix for G4FPE_DEBUG on by A. Howard ( and T. Koi)
31// 08-08-06 delete unnecessary and harmed declaration; Bug Report[857]
32//
33#include "G4NeutronHPFission.hh"
34
35 G4NeutronHPFission::G4NeutronHPFission()
36 :G4HadronicInteraction("NeutronHPFission")
37 {
38 SetMinEnergy( 0.0 );
39 SetMaxEnergy( 20.*MeV );
40 if(!getenv("G4NEUTRONHPDATA"))
41 throw G4HadronicException(__FILE__, __LINE__, "Please setenv G4NEUTRONHPDATA to point to the neutron cross-section files.");
42 dirName = getenv("G4NEUTRONHPDATA");
43 G4String tString = "/Fission/";
44 dirName = dirName + tString;
45 numEle = G4Element::GetNumberOfElements();
46 theFission = new G4NeutronHPChannel[numEle];
47
48 for (G4int i=0; i<numEle; i++)
49 {
50 if((*(G4Element::GetElementTable()))[i]->GetZ()>89)
51 {
52 theFission[i].Init((*(G4Element::GetElementTable()))[i], dirName);
53 theFission[i].Register(&theFS);
54 }
55 }
56 }
57
58 G4NeutronHPFission::~G4NeutronHPFission()
59 {
60 delete [] theFission;
61 }
62
63 #include "G4NeutronHPThermalBoost.hh"
64 G4HadFinalState * G4NeutronHPFission::ApplyYourself(const G4HadProjectile& aTrack, G4Nucleus& )
65 {
66 const G4Material * theMaterial = aTrack.GetMaterial();
67 G4int n = theMaterial->GetNumberOfElements();
68 G4int index = theMaterial->GetElement(0)->GetIndex();
69 if(n!=1)
70 {
71 xSec = new G4double[n];
72 G4double sum=0;
73 G4int i;
74 const G4double * NumAtomsPerVolume = theMaterial->GetVecNbOfAtomsPerVolume();
75 G4double rWeight;
76 G4NeutronHPThermalBoost aThermalE;
77 for (i=0; i<n; i++)
78 {
79 index = theMaterial->GetElement(i)->GetIndex();
80 rWeight = NumAtomsPerVolume[i];
81 xSec[i] = theFission[index].GetXsec(aThermalE.GetThermalEnergy(aTrack,
82 theMaterial->GetElement(i),
83 theMaterial->GetTemperature()));
84 xSec[i] *= rWeight;
85 sum+=xSec[i];
86 }
87 G4double random = G4UniformRand();
88 G4double running = 0;
89 for (i=0; i<n; i++)
90 {
91 running += xSec[i];
92 index = theMaterial->GetElement(i)->GetIndex();
93 //if(random<=running/sum) break;
94 if( sum == 0 || random <= running/sum ) break;
95 }
96 delete [] xSec;
97 }
98 return theFission[index].ApplyYourself(aTrack);
99 }
100
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