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G4NeutronHPorLFission.cc
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27 // 05-11-21 NeutronHP or Low Energy Parameterization Models
28 // Implemented by T. Koi (SLAC/SCCS)
29 // If NeutronHP data do not available for an element, then Low Energy
30 // Parameterization models handle the interactions of the element.
31 // 080319 Compilation warnings - gcc-4.3.0 fix by T. Koi
32 //
33 
34 // neutron_hp -- source file
35 // J.P. Wellisch, Nov-1996
36 // A prototype of the low energy neutron transport model.
37 //
38 #include "G4NeutronHPorLFission.hh"
39 #include "G4SystemOfUnits.hh"
40 #include "G4NeutronHPFissionFS.hh"
41 
43  :G4HadronicInteraction("NeutronHPorLFission")
44 {
45  SetMinEnergy(0.*eV);
46  SetMaxEnergy(20.*MeV);
47 
48  if( !getenv("G4NEUTRONHPDATA") )
49  throw G4HadronicException(__FILE__, __LINE__, "Please setenv G4NEUTRONHPDATA to point to the neutron cross-section files.");
50 
51  dirName = getenv("G4NEUTRONHPDATA");
52  G4String tString = "/Fission/";
53  dirName = dirName + tString;
54 // G4cout <<"G4NeutronHPorLFission::G4NeutronHPorLFission testit "<<dirName<<G4endl;
55  unavailable_elements.clear();
56 
58  theFission = new G4NeutronHPChannel[numEle];
59 
60  for ( G4int i = 0; i < numEle ; i++)
61  {
62  if ( (*(G4Element::GetElementTable()))[i]-> GetZ() > 87 ) //TK modified for ENDF-VII
63  {
64  theFission[i].Init((*(G4Element::GetElementTable()))[i], dirName);
65  try { while(!theFission[i].Register(&theFS)) ; }
66  catch ( G4HadronicException )
67  {
68  unavailable_elements.insert ( (*(G4Element::GetElementTable()))[i]->GetName() );
69  }
70  }
71  }
72 
73  if ( unavailable_elements.size() > 0 )
74  {
75  std::set< G4String>::iterator it;
76  G4cout << "HP Fission data are not available for thess elements "<< G4endl;
77  for ( it = unavailable_elements.begin() ; it != unavailable_elements.end() ; it++ )
78  {
79  G4cout << *it << G4endl;
80  }
81  G4cout << "Low Energy Parameterization Models will be used."<< G4endl;
82  }
83 
84  createXSectionDataSet();
85 }
86 
88 {
89  delete [] theFission;
90  delete theDataSet;
91 }
92 
94 
96 {
97  const G4Material * theMaterial = aTrack.GetMaterial();
98  G4int n = theMaterial->GetNumberOfElements();
99  G4int index = theMaterial->GetElement(0)->GetIndex();
100  if(n!=1)
101  {
102  G4int i;
103  xSec = new G4double[n];
104  G4double sum=0;
105  const G4double * NumAtomsPerVolume = theMaterial->GetVecNbOfAtomsPerVolume();
106  G4double rWeight;
107  G4NeutronHPThermalBoost aThermalE;
108  for (i=0; i<n; i++)
109  {
110  index = theMaterial->GetElement(i)->GetIndex();
111  rWeight = NumAtomsPerVolume[i];
112  G4double x = aThermalE.GetThermalEnergy(aTrack, theMaterial->GetElement(i), theMaterial->GetTemperature());
113 
114  //xSec[i] = theFission[index].GetXsec(aThermalE.GetThermalEnergy(aTrack,
115  // theMaterial->GetElement(i),
116  // theMaterial->GetTemperature()));
117  xSec[i] = theFission[index].GetXsec(x);
118 
119  xSec[i] *= rWeight;
120  sum+=xSec[i];
121  }
122  G4double random = G4UniformRand();
123  G4double running = 0;
124  for (i=0; i<n; i++)
125  {
126  running += xSec[i];
127  index = theMaterial->GetElement(i)->GetIndex();
128  if(random<=running/sum) break;
129  }
130  delete [] xSec;
131  // it is element-wise initialised.
132  }
133  return theFission[index].ApplyYourself(aTrack);
134 }
135 
136 
137 
139 {
140  if ( unavailable_elements.find( name ) == unavailable_elements.end() )
141  return TRUE;
142  else
143  return FALSE;
144 }
145 
146 
147 
148 void G4NeutronHPorLFission::createXSectionDataSet()
149 {
150  theDataSet = new G4NeutronHPorLFissionData ( theFission , &unavailable_elements );
151 }
152 const std::pair<G4double, G4double> G4NeutronHPorLFission::GetFatalEnergyCheckLevels() const
153 {
154  //return std::pair<G4double, G4double>(10*perCent,10*GeV);
155  return std::pair<G4double, G4double>(10*perCent,DBL_MAX);
156 }