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G4ParticleHPFission.cc
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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 // P. Arce, June-2014 Conversion neutron_hp to particle_hp
34 //
35 #include "G4ParticleHPFission.hh"
36 #include "G4ParticleHPFissionFS.hh"
37 #include "G4SystemOfUnits.hh"
38 #include "G4ParticleHPManager.hh"
39 #include "G4Threading.hh"
40 
42  :G4HadronicInteraction("NeutronHPFission")
43  ,theFission(NULL)
44  ,numEle(0)
45  {
46  SetMinEnergy( 0.0 );
47  SetMaxEnergy( 20.*MeV );
48 /*
49  if(!std::getenv("G4NEUTRONHPDATA"))
50  throw G4HadronicException(__FILE__, __LINE__, "Please setenv G4NEUTRONHPDATA to point to the neutron cross-section files.");
51  dirName = std::getenv("G4NEUTRONHPDATA");
52  G4String tString = "/Fission";
53  dirName = dirName + tString;
54  numEle = G4Element::GetNumberOfElements();
55  //theFission = new G4ParticleHPChannel[numEle];
56 
57  //for (G4int i=0; i<numEle; i++)
58  //{
59  //if((*(G4Element::GetElementTable()))[i]->GetZ()>89)
60  // if((*(G4Element::GetElementTable()))[i]->GetZ()>87) //TK modified for ENDF-VII
61  // {
62  // theFission[i].Init((*(G4Element::GetElementTable()))[i], dirName);
63  // theFission[i].Register(&theFS);
64  // }
65  //}
66 
67  for ( G4int i = 0 ; i < numEle ; i++ )
68  {
69  theFission.push_back( new G4ParticleHPChannel );
70  if((*(G4Element::GetElementTable()))[i]->GetZ()>87) //TK modified for ENDF-VII
71  {
72  (*theFission[i]).Init((*(G4Element::GetElementTable()))[i], dirName);
73  (*theFission[i]).Register(&theFS);
74  }
75  }
76 */
77  }
78 
80  {
81  //Vector is shared, only master deletes it
82  //delete [] theFission;
83  if ( ! G4Threading::IsMasterThread() ) {
84  if ( theFission != NULL ) {
85  for ( std::vector<G4ParticleHPChannel*>::iterator
86  it = theFission->begin() ; it != theFission->end() ; it++ ) {
87  delete *it;
88  }
89  theFission->clear();
90  }
91  }
92  }
93 
96  {
97 
99  const G4Material * theMaterial = aTrack.GetMaterial();
100  G4int n = theMaterial->GetNumberOfElements();
101  G4int index = theMaterial->GetElement(0)->GetIndex();
102  if(n!=1)
103  {
104  G4double* xSec = new G4double[n];
105  G4double sum=0;
106  G4int i;
107  const G4double * NumAtomsPerVolume = theMaterial->GetVecNbOfAtomsPerVolume();
108  G4double rWeight;
109  G4ParticleHPThermalBoost aThermalE;
110  for (i=0; i<n; i++)
111  {
112  index = theMaterial->GetElement(i)->GetIndex();
113  rWeight = NumAtomsPerVolume[i];
114  xSec[i] = ((*theFission)[index])->GetXsec(aThermalE.GetThermalEnergy(aTrack,
115  theMaterial->GetElement(i),
116  theMaterial->GetTemperature()));
117  xSec[i] *= rWeight;
118  sum+=xSec[i];
119  }
120  G4double random = G4UniformRand();
121  G4double running = 0;
122  for (i=0; i<n; i++)
123  {
124  running += xSec[i];
125  index = theMaterial->GetElement(i)->GetIndex();
126  //if(random<=running/sum) break;
127  if( sum == 0 || random <= running/sum ) break;
128  }
129  delete [] xSec;
130  }
131  //return theFission[index].ApplyYourself(aTrack); //-2:Marker for Fission
132  G4HadFinalState* result = ((*theFission)[index])->ApplyYourself(aTrack,-2);
133 
134  //Overwrite target parameters
135  aNucleus.SetParameters(G4ParticleHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargA(),G4ParticleHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargZ());
136  const G4Element* target_element = (*G4Element::GetElementTable())[index];
137  const G4Isotope* target_isotope=NULL;
138  G4int iele = target_element->GetNumberOfIsotopes();
139  for ( G4int j = 0 ; j != iele ; j++ ) {
140  target_isotope=target_element->GetIsotope( j );
141  if ( target_isotope->GetN() == G4ParticleHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargA() ) break;
142  }
143  //G4cout << "Target Material of this reaction is " << theMaterial->GetName() << G4endl;
144  //G4cout << "Target Element of this reaction is " << target_element->GetName() << G4endl;
145  //G4cout << "Target Isotope of this reaction is " << target_isotope->GetName() << G4endl;
146  aNucleus.SetIsotope( target_isotope );
147 
149  return result;
150  }
151 
152 const std::pair<G4double, G4double> G4ParticleHPFission::GetFatalEnergyCheckLevels() const
153 {
154  // max energy non-conservation is mass of heavy nucleus
155  //return std::pair<G4double, G4double>(5*perCent,250*GeV);
156  return std::pair<G4double, G4double>(5*perCent,DBL_MAX);
157 }
158 /*
159 void G4ParticleHPFission::addChannelForNewElement()
160 {
161  for ( G4int i = numEle ; i < (G4int)G4Element::GetNumberOfElements() ; i++ )
162  {
163  theFission.push_back( new G4ParticleHPChannel );
164  if ( (*(G4Element::GetElementTable()))[i]->GetZ() > 87 ) //TK modified for ENDF-VII
165  {
166  G4cout << "G4ParticleHPFission Prepairing Data for the new element of " << (*(G4Element::GetElementTable()))[i]->GetName() << G4endl;
167  (*theFission[i]).Init((*(G4Element::GetElementTable()))[i], dirName);
168  (*theFission[i]).Register(&theFS);
169  }
170  }
171  numEle = (G4int)G4Element::GetNumberOfElements();
172 }
173 */
174 
176 {
178 }
180 {
182 }
184 {
185 
187 
188  theFission = hpmanager->GetFissionFinalStates();
189 
190  if ( G4Threading::IsMasterThread() ) {
191 
192  if ( theFission == NULL ) theFission = new std::vector<G4ParticleHPChannel*>;
193 
194  if ( numEle == (G4int)G4Element::GetNumberOfElements() ) return;
195 
196  if ( theFission->size() == G4Element::GetNumberOfElements() ) {
198  return;
199  }
200 
201  if ( !std::getenv("G4NEUTRONHPDATA") )
202  throw G4HadronicException(__FILE__, __LINE__, "Please setenv G4NEUTRONHPDATA to point to the neutron cross-section files.");
203  dirName = std::getenv("G4NEUTRONHPDATA");
204  G4String tString = "/Fission";
205  dirName = dirName + tString;
206 
207  for ( G4int i = numEle ; i < (G4int)G4Element::GetNumberOfElements() ; i++ ) {
208  theFission->push_back( new G4ParticleHPChannel );
209  if ((*(G4Element::GetElementTable()))[i]->GetZ()>87) { //TK modified for ENDF-VII
210  ((*theFission)[i])->Init((*(G4Element::GetElementTable()))[i], dirName);
211  ((*theFission)[i])->Register( new G4ParticleHPFissionFS );
212  }
213  }
214 
216 
217  }
218 
220 }
221 
222 void G4ParticleHPFission::ModelDescription(std::ostream& outFile) const
223 {
224  outFile << "High Precision model based on Evaluated Nuclear Data Files (ENDF) for induced fission reaction of neutrons below 20MeV\n";
225 }