G4NeutronHPFFFissionFS.cc

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//
// neutron_hp -- source file
// J.P. Wellisch, Nov-1996
// A prototype of the low energy neutron transport model.
//
#include "G4NeutronHPFFFissionFS.hh"
#include "G4SystemOfUnits.hh"

void G4NeutronHPFFFissionFS::Init (G4double A, G4double Z, G4int M, G4String & dirName, G4String & )
{
   //G4cout << "G4NeutronHPFFFissionFS::Init" << G4endl;
   G4String aString = "FF";

   G4String tString = dirName;
   G4bool dbool;
   G4NeutronHPDataUsed aFile = theNames.GetName(static_cast<G4int>(A), static_cast<G4int>(Z), M, tString, aString , dbool);
   G4String filename = aFile.GetName();
   theBaseA = aFile.GetA();
   theBaseZ = aFile.GetZ();

//3456
   if ( !dbool || ( Z < 2.5 && ( std::abs(theBaseZ-Z)>0.0001 || std::abs(theBaseA-A)>0.0001) ) )
   {
      hasAnyData = false;
      hasFSData = false; 
      hasXsec = false;
      return; // no data for exactly this isotope.
   }
   std::ifstream theData(filename, std::ios::in);
   G4double dummy;
   if ( !theData )
   {
      theData.close();
      hasFSData = false;
      hasXsec = false;
      hasAnyData = false;
      return; // no data for this FS for this isotope
   }


   hasFSData = true; 
      //          MT              Energy            FPS    Yield
      //std::map< int , std::map< double , std::map< int , double >* >* > FisionProductYieldData; 
   while ( theData.good() )
   {
      G4int iMT, iMF;
      G4int imax;
      //Reading the data
      //         MT       MF       AWR
      theData >> iMT >> iMF >> dummy;
      //         nBlock 
      theData >> imax;
      //if ( !theData.good() ) continue;
      //        Ei                   FPS     Yield
      std::map< G4double , std::map< G4int , G4double >* >* mEnergyFSPData = new std::map< G4double , std::map< G4int , G4double >* >;

      std::map< G4double , G4int >* mInterporation = new std::map< G4double , G4int >;
      for ( G4int i = 0 ; i <= imax ; i++ ) 
      {
       
         G4double YY=0.0; 
         G4double Ei;
         G4int jmax;
         G4int ip;
         //        energy of incidnece neutron 
         theData >> Ei;
         //        Number of data set followings 
         theData >> jmax;
         //         interpolation scheme
         theData >> ip;
         mInterporation->insert( std::pair<G4double,G4int>(Ei*eV,ip) );
         //         nNumber  nIP
         std::map<G4int,G4double>* mFSPYieldData = new std::map<G4int,G4double>;
         for ( G4int j = 0 ; j < jmax ; j++ ) 
         {
            G4int FSP;
            G4int mFSP;
            G4double Y;
            theData >> FSP >> mFSP >> Y;
            G4int k = FSP*100+mFSP;
            YY = YY + Y;
            //if ( iMT == 454 )G4cout << iMT << " " << i << " " << j << " " <<  k << " " << Y << " " << YY << G4endl;
            mFSPYieldData->insert( std::pair<G4int,G4double>( k , YY ) );
         }
         mEnergyFSPData->insert( std::pair<G4double,std::map<G4int,G4double>*>(Ei*eV,mFSPYieldData) ); 
      }

      FissionProductYieldData.insert( std::pair< G4int , std::map< G4double , std::map< G4int , G4double >* >* > (iMT,mEnergyFSPData));
      mMTInterpolation.insert( std::pair<G4int,std::map<G4double,G4int>*> (iMT,mInterporation) ); 
   } 
   theData.close();
}
  
G4DynamicParticleVector * G4NeutronHPFFFissionFS::ApplyYourself(G4int nNeutrons)
{  
   G4DynamicParticleVector * aResult;
//    G4cout <<"G4NeutronHPFFFissionFS::ApplyYourself +"<<G4endl;
   aResult = G4NeutronHPFissionBaseFS::ApplyYourself(nNeutrons);    
   return aResult;
}

void G4NeutronHPFFFissionFS::GetAFissionFragment( G4double energy , G4int& fragZ , G4int& fragA , G4int& fragM )
{
   //G4cout << "G4NeutronHPFFFissionFS::GetAFissionFragment " << G4endl;

   G4double rand =G4UniformRand();
   //G4cout << rand << G4endl;

   std::map< G4double , std::map< G4int , G4double >* >* mEnergyFSPData = FissionProductYieldData.find( 454 )->second;
    
   //It is not clear that the treatment of the scheme 2 on two-dimensional interpolation. 
   //So, here just use the closest energy point array of yield data. 
   //TK120531
   G4double key_energy = DBL_MAX;
   if ( mEnergyFSPData->size() == 1 )
   {
      key_energy = mEnergyFSPData->begin()->first;
   }
   else
   {
      //Find closest energy point
      G4double Dmin=DBL_MAX; 
      G4int i = 0;
      for ( std::map< G4double , std::map< G4int , G4double >* >::iterator it = mEnergyFSPData->begin() ; 
      it != mEnergyFSPData->end() ; it++ )
      {
         G4double e = (it->first);
         G4double d = std::fabs ( energy - e ); 
         if ( d < Dmin ) 
         {
            Dmin = d;
            key_energy = e;
         }
         i++;
      }
   }

   std::map<G4int,G4double>* mFSPYieldData = (*mEnergyFSPData)[key_energy];

   G4int ifrag=0;
   G4double ceilling = mFSPYieldData->rbegin()->second; // Becaseu of numerical accuracy, this is not always 2 
   for ( std::map<G4int,G4double>::iterator it = mFSPYieldData->begin() ; it != mFSPYieldData->end() ; it++ )
   {
      //if ( ( rand - it->second/ceilling ) < 1.0e-6 ) std::cout << rand - it->second/ceilling << std::endl;
      if ( rand <= it->second/ceilling ) 
      {  
         //G4cout << it->first << " " << it->second/ceilling << G4endl;
         ifrag = it->first;
         break;
      }
   }

   fragZ = ifrag/100000;
   fragA = (ifrag%100000)/100;
   fragM = (ifrag%100);

   //G4cout << fragZ << " " << fragA << " " << fragM << G4endl;
}