source: trunk/source/processes/hadronic/models/neutron_hp/src/G4NeutronHPorLFission.cc@ 1036

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//
// 05-11-21 NeutronHP or Low Energy Parameterization Models 
//          Implemented by T. Koi (SLAC/SCCS)
//          If NeutronHP data do not available for an element, then Low Energy 
//          Parameterization models handle the interactions of the element.
// 080319 Compilation warnings - gcc-4.3.0 fix by T. Koi
//

// neutron_hp -- source file
// J.P. Wellisch, Nov-1996
// A prototype of the low energy neutron transport model.
//
#include "G4NeutronHPorLFission.hh"
#include "G4NeutronHPFissionFS.hh"

G4NeutronHPorLFission::G4NeutronHPorLFission()
  :G4HadronicInteraction("NeutronHPorLFission")
{
   SetMinEnergy(0.*eV);
   SetMaxEnergy(20.*MeV);

   if( !getenv("G4NEUTRONHPDATA") ) 
       throw G4HadronicException(__FILE__, __LINE__, "Please setenv G4NEUTRONHPDATA to point to the neutron cross-section files.");

   dirName = getenv("G4NEUTRONHPDATA");
   G4String tString = "/Fission/";
   dirName = dirName + tString;
//    G4cout <<"G4NeutronHPorLFission::G4NeutronHPorLFission testit "<<dirName<<G4endl;
   unavailable_elements.clear();

   numEle = G4Element::GetNumberOfElements();
   theFission = new G4NeutronHPChannel[numEle];

   for ( G4int i = 0; i < numEle ; i++)
   {
      if ( (*(G4Element::GetElementTable()))[i]-> GetZ() > 89 )
      {
         theFission[i].Init((*(G4Element::GetElementTable()))[i], dirName);
         try { while(!theFission[i].Register(&theFS)) ; }
         catch ( G4HadronicException )
         {
             unavailable_elements.insert ( (*(G4Element::GetElementTable()))[i]->GetName() ); 
         }
      } 
   }

   if ( unavailable_elements.size() > 0 ) 
   {
      std::set< G4String>::iterator it;
      G4cout << "HP Fission data are not available for thess  elements "<< G4endl;
      for ( it = unavailable_elements.begin() ; it != unavailable_elements.end() ; it++ )
      {
            G4cout << *it << G4endl;
      }
      G4cout << "Low Energy Parameterization Models will be used."<< G4endl;
   }

   createXSectionDataSet();
}
  
G4NeutronHPorLFission::~G4NeutronHPorLFission()
{
   delete [] theFission;
   delete theDataSet; 
}
  
#include "G4NeutronHPThermalBoost.hh"
  
G4HadFinalState * G4NeutronHPorLFission::ApplyYourself(const G4HadProjectile& aTrack, G4Nucleus& )
{
   const G4Material * theMaterial = aTrack.GetMaterial();
   G4int n = theMaterial->GetNumberOfElements();
   G4int index = theMaterial->GetElement(0)->GetIndex();
   if(n!=1)
   {
      G4int i;
      xSec = new G4double[n];
      G4double sum=0;
      const G4double * NumAtomsPerVolume = theMaterial->GetVecNbOfAtomsPerVolume();
      G4double rWeight;    
      G4NeutronHPThermalBoost aThermalE;
      for (i=0; i<n; i++)
      {
        index = theMaterial->GetElement(i)->GetIndex();
        rWeight = NumAtomsPerVolume[i];
        G4double x = aThermalE.GetThermalEnergy(aTrack, theMaterial->GetElement(i), theMaterial->GetTemperature());

        //xSec[i] = theFission[index].GetXsec(aThermalE.GetThermalEnergy(aTrack,
        //                                                                   theMaterial->GetElement(i),
        //                                                                   theMaterial->GetTemperature()));
        xSec[i] = theFission[index].GetXsec(x);

        xSec[i] *= rWeight;
        sum+=xSec[i];
      }
      G4double random = G4UniformRand();
      G4double running = 0;
      for (i=0; i<n; i++)
      {
        running += xSec[i];
        index = theMaterial->GetElement(i)->GetIndex();
        if(random<=running/sum) break;
      }
      delete [] xSec;
      // it is element-wise initialised.
    }
    return theFission[index].ApplyYourself(aTrack); 
}



G4bool G4NeutronHPorLFission::IsThisElementOK( G4String name )
{
   if ( unavailable_elements.find( name ) == unavailable_elements.end() ) 
      return TRUE;
   else 
      return FALSE; 
}



void G4NeutronHPorLFission::createXSectionDataSet()
{
   theDataSet = new G4NeutronHPorLFissionData ( theFission , &unavailable_elements );
}