G4NeutronHPFission.cc

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//
// neutron_hp -- source file
// J.P. Wellisch, Nov-1996
// A prototype of the low energy neutron transport model.
//
// 070523 bug fix for G4FPE_DEBUG on by A. Howard ( and T. Koi)
// 08-08-06 delete unnecessary and harmed declaration; Bug Report[857]
//
#include "G4NeutronHPFission.hh"
#include "G4SystemOfUnits.hh"

#include "G4NeutronHPManager.hh"

  G4NeutronHPFission::G4NeutronHPFission()
    :G4HadronicInteraction("NeutronHPFission")
  ,theFission(NULL)
  ,numEle(0)
  {
    SetMinEnergy( 0.0 );
    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;
    numEle = G4Element::GetNumberOfElements();
    //theFission = new G4NeutronHPChannel[numEle];

    //for (G4int i=0; i<numEle; i++)
    //{ 
      //if((*(G4Element::GetElementTable()))[i]->GetZ()>89)
    //  if((*(G4Element::GetElementTable()))[i]->GetZ()>87) //TK modified for ENDF-VII
    //  {
    //    theFission[i].Init((*(G4Element::GetElementTable()))[i], dirName);
    //    theFission[i].Register(&theFS);
    //  }
    //}

    for ( G4int i = 0 ; i < numEle ; i++ ) 
    {
      theFission.push_back( new G4NeutronHPChannel );
      if((*(G4Element::GetElementTable()))[i]->GetZ()>87) //TK modified for ENDF-VII
      {
       (*theFission[i]).Init((*(G4Element::GetElementTable()))[i], dirName);
       (*theFission[i]).Register(&theFS);
      }
    }
*/
  }
  
  G4NeutronHPFission::~G4NeutronHPFission()
  {
    //delete [] theFission;
     for ( std::vector<G4NeutronHPChannel*>::iterator 
           it = (*theFission).begin() ; it != (*theFission).end() ; it++ )
     {
        delete *it;
     }
     (*theFission).clear();
  }
  
  #include "G4NeutronHPThermalBoost.hh"
  G4HadFinalState * G4NeutronHPFission::ApplyYourself(const G4HadProjectile& aTrack, G4Nucleus& aNucleus )
  {

    //if ( numEle < (G4int)G4Element::GetNumberOfElements() ) addChannelForNewElement();

    G4NeutronHPManager::GetInstance()->OpenReactionWhiteBoard();
    const G4Material * theMaterial = aTrack.GetMaterial();
    G4int n = theMaterial->GetNumberOfElements();
    G4int index = theMaterial->GetElement(0)->GetIndex();
    if(n!=1)
    {
      xSec = new G4double[n];
      G4double sum=0;
      G4int i;
      const G4double * NumAtomsPerVolume = theMaterial->GetVecNbOfAtomsPerVolume();
      G4double rWeight;    
      G4NeutronHPThermalBoost aThermalE;
      for (i=0; i<n; i++)
      {
        index = theMaterial->GetElement(i)->GetIndex();
        rWeight = NumAtomsPerVolume[i];
        xSec[i] = (*(*theFission)[index]).GetXsec(aThermalE.GetThermalEnergy(aTrack,
                                                                      theMaterial->GetElement(i),
                                                                      theMaterial->GetTemperature()));
        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;
        if( sum == 0 ||  random <= running/sum ) break;
      }
      delete [] xSec;
    }
    //return theFission[index].ApplyYourself(aTrack);                 //-2:Marker for Fission
    G4HadFinalState* result = (*(*theFission)[index]).ApplyYourself(aTrack,-2);

    //Overwrite target parameters
    aNucleus.SetParameters(G4NeutronHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargA(),G4NeutronHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargZ());
    const G4Element* target_element = (*G4Element::GetElementTable())[index];
    const G4Isotope* target_isotope=NULL;
    G4int iele = target_element->GetNumberOfIsotopes();
    for ( G4int j = 0 ; j != iele ; j++ ) { 
       target_isotope=target_element->GetIsotope( j );
       if ( target_isotope->GetN() == G4NeutronHPManager::GetInstance()->GetReactionWhiteBoard()->GetTargA() ) break; 
    }
    //G4cout << "Target Material of this reaction is " << theMaterial->GetName() << G4endl;
    //G4cout << "Target Element of this reaction is " << target_element->GetName() << G4endl;
    //G4cout << "Target Isotope of this reaction is " << target_isotope->GetName() << G4endl;
    aNucleus.SetIsotope( target_isotope );

    G4NeutronHPManager::GetInstance()->CloseReactionWhiteBoard();
    return result; 
  }

const std::pair<G4double, G4double> G4NeutronHPFission::GetFatalEnergyCheckLevels() const
{
        // max energy non-conservation is mass of heavy nucleus
        //return std::pair<G4double, G4double>(5*perCent,250*GeV);
        return std::pair<G4double, G4double>(5*perCent,DBL_MAX);
}


/*
void G4NeutronHPFission::addChannelForNewElement()
{
   for ( G4int i = numEle ; i < (G4int)G4Element::GetNumberOfElements() ; i++ ) 
   {
      theFission.push_back( new G4NeutronHPChannel );
      if ( (*(G4Element::GetElementTable()))[i]->GetZ() > 87 ) //TK modified for ENDF-VII
      {
         G4cout << "G4NeutronHPFission Prepairing Data for the new element of " << (*(G4Element::GetElementTable()))[i]->GetName() << G4endl;
         (*theFission[i]).Init((*(G4Element::GetElementTable()))[i], dirName);
         (*theFission[i]).Register(&theFS);
      }
   }
   numEle = (G4int)G4Element::GetNumberOfElements();
}
*/

G4int G4NeutronHPFission::GetVerboseLevel() const
{
   return G4NeutronHPManager::GetInstance()->GetVerboseLevel();
}
void G4NeutronHPFission::SetVerboseLevel( G4int newValue ) 
{
   G4NeutronHPManager::GetInstance()->SetVerboseLevel(newValue);
}
void G4NeutronHPFission::BuildPhysicsTable(const G4ParticleDefinition&)
{
   G4NeutronHPManager* hpmanager = G4NeutronHPManager::GetInstance();

   theFission = hpmanager->GetFissionFinalStates();

   if ( !G4Threading::IsWorkerThread() ) {

      if ( theFission == NULL ) theFission = new std::vector<G4NeutronHPChannel*>;

      if ( numEle == (G4int)G4Element::GetNumberOfElements() ) return;

      if ( theFission->size() == G4Element::GetNumberOfElements() ) {
         numEle = G4Element::GetNumberOfElements();
         return;
      }

      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;

      for ( G4int i = numEle ; i < (G4int)G4Element::GetNumberOfElements() ; i++ ) {
         (*theFission).push_back( new G4NeutronHPChannel );
         if ((*(G4Element::GetElementTable()))[i]->GetZ()>87) { //TK modified for ENDF-VII
            (*(*theFission)[i]).Init((*(G4Element::GetElementTable()))[i], dirName);
            (*(*theFission)[i]).Register(&theFS);
         }
      }

      hpmanager->RegisterFissionFinalStates( theFission );

   }
   numEle = G4Element::GetNumberOfElements();
}