source: trunk/source/processes/hadronic/models/neutron_hp/src/G4NeutronHPInelasticData.cc @ 829

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//
// neutron_hp -- source file
// J.P. Wellisch, Nov-1996
// A prototype of the low energy neutron transport model.
//
// 070523 add neglecting doppler broadening on the fly. T. Koi
// 070613 fix memory leaking by T. Koi
// 071002 enable cross section dump by T. Koi
//
#include "G4NeutronHPInelasticData.hh"
#include "G4Neutron.hh"
#include "G4ElementTable.hh"
#include "G4NeutronHPData.hh"

G4bool G4NeutronHPInelasticData::IsApplicable(const G4DynamicParticle*aP, const G4Element*)
{
  G4bool result = true;
  G4double eKin = aP->GetKineticEnergy();
  if(eKin>20*MeV||aP->GetDefinition()!=G4Neutron::Neutron()) result = false;
  return result;
}

G4NeutronHPInelasticData::G4NeutronHPInelasticData()
{
// TKDB
   theCrossSections = 0;
  BuildPhysicsTable(*G4Neutron::Neutron());
}
   
G4NeutronHPInelasticData::~G4NeutronHPInelasticData()
{
// TKDB
  if ( theCrossSections != 0 )
  {  theCrossSections->clearAndDestroy(); }
  delete theCrossSections;
}
   
void G4NeutronHPInelasticData::BuildPhysicsTable(const G4ParticleDefinition& aP)
{
  if(&aP!=G4Neutron::Neutron()) 
     throw G4HadronicException(__FILE__, __LINE__, "Attempt to use NeutronHP data for particles other than neutrons!!!");  
  size_t numberOfElements = G4Element::GetNumberOfElements();
//  theCrossSections = new G4PhysicsTable( numberOfElements );
// TKDB
   if ( theCrossSections == 0 )
   { theCrossSections = new G4PhysicsTable( numberOfElements ); }

  // make a PhysicsVector for each element

  static const G4ElementTable *theElementTable = G4Element::GetElementTable();
  for( size_t i=0; i<numberOfElements; ++i )
  {
     G4PhysicsVector* physVec = G4NeutronHPData::
      Instance()->MakePhysicsVector((*theElementTable)[i], this);
     theCrossSections->push_back(physVec);
  }
}

void G4NeutronHPInelasticData::DumpPhysicsTable(const G4ParticleDefinition& aP)
{
  if(&aP!=G4Neutron::Neutron()) 
     throw G4HadronicException(__FILE__, __LINE__, "Attempt to use NeutronHP data for particles other than neutrons!!!");  

//
// Dump element based cross section
// range 10e-5 eV to 20 MeV
// 10 point per decade
// in barn
//

   G4cout << G4endl;
   G4cout << G4endl;
   G4cout << "Inelastic Cross Section of Neutron HP"<< G4endl;
   G4cout << "(Pointwise cross-section at 0 Kelvin.)" << G4endl;
   G4cout << G4endl;
   G4cout << "Name of Element" << G4endl;
   G4cout << "Energy[eV]  XS[barn]" << G4endl;
   G4cout << G4endl;

   size_t numberOfElements = G4Element::GetNumberOfElements();
   static const G4ElementTable *theElementTable = G4Element::GetElementTable();

   for ( size_t i = 0 ; i < numberOfElements ; ++i )
   {

      G4cout << (*theElementTable)[i]->GetName() << G4endl;

      G4int ie = 0;

      for ( ie = 0 ; ie < 130 ; ie++ )
      {
         G4double eKinetic = 1.0e-5 * std::pow ( 10.0 , ie/10.0 ) *eV;
         G4bool outOfRange = false;

         if ( eKinetic < 20*MeV )
         {
            G4cout << eKinetic/eV << " " << (*((*theCrossSections)(i))).GetValue(eKinetic, outOfRange)/barn << G4endl;
         }

      }

      G4cout << G4endl;
   }

  //G4cout << "G4NeutronHPInelasticData::DumpPhysicsTable still to be implemented"<<G4endl;
}

#include "G4NucleiPropertiesTable.hh"

G4double G4NeutronHPInelasticData::
GetCrossSection(const G4DynamicParticle* aP, const G4Element*anE, G4double aT)
{
  G4double result = 0;
  G4bool outOfRange;
  G4int index = anE->GetIndex();

  // prepare neutron
  G4double eKinetic = aP->GetKineticEnergy();

  // T. K. 
  if ( getenv( "G4NEUTRONHP_NEGLECT_DOPPLER" ) )
  {
     G4double factor = 1.0;
     if ( eKinetic < aT * k_Boltzmann ) 
     {
        // below 0.1 eV neutrons 
        // Have to do some, but now just igonre.   
        // Will take care after performance check.  
        // factor = factor * targetV;
     }
     return ( (*((*theCrossSections)(index))).GetValue(eKinetic, outOfRange) )* factor; 
  }   

  G4ReactionProduct theNeutron( aP->GetDefinition() );
  theNeutron.SetMomentum( aP->GetMomentum() );
  theNeutron.SetKineticEnergy( eKinetic );

  // prepare thermal nucleus
  G4Nucleus aNuc;
  G4double eps = 0.0001;
  G4double theA = anE->GetN();
  G4double theZ = anE->GetZ();
  G4double eleMass; 
  eleMass = ( G4NucleiPropertiesTable::GetNuclearMass(static_cast<G4int>(theZ+eps), static_cast<G4int>(theA+eps))
             ) / G4Neutron::Neutron()->GetPDGMass();
  
  G4ReactionProduct boosted;
  G4double aXsection;
  
  // MC integration loop
  G4int counter = 0;
  G4int failCount = 0;
  G4double buffer = 0;
  G4int size = G4int(std::max(10., aT/60*kelvin));
  G4ThreeVector neutronVelocity = 1./G4Neutron::Neutron()->GetPDGMass()*theNeutron.GetMomentum();
  G4double neutronVMag = neutronVelocity.mag();

  while(counter == 0 || std::abs(buffer-result/std::max(1,counter)) > 0.01*buffer)
  {
    if(counter) buffer = result/counter;
    while (counter<size)
    {
      counter ++;
      G4ReactionProduct aThermalNuc = aNuc.GetThermalNucleus(eleMass, aT);
      boosted.Lorentz(theNeutron, aThermalNuc);
      G4double theEkin = boosted.GetKineticEnergy();
      aXsection = (*((*theCrossSections)(index))).GetValue(theEkin, outOfRange);
      if(aXsection <0) 
      {
        if(failCount<1000)
        {
          failCount++;
          counter--;
          continue;
        }
        else
        {
          aXsection = 0;
        }
      }
      // velocity correction.
      G4ThreeVector targetVelocity = 1./aThermalNuc.GetMass()*aThermalNuc.GetMomentum();
      aXsection *= (targetVelocity-neutronVelocity).mag()/neutronVMag;
      result += aXsection;
    }
    size += size;
  }
  result /= counter;
/*
  // Checking impact of  G4NEUTRONHP_NEGLECT_DOPPLER
  G4cout << " result " << result << " " 
         << (*((*theCrossSections)(index))).GetValue(eKinetic, outOfRange) << " " 
         << (*((*theCrossSections)(index))).GetValue(eKinetic, outOfRange) /result << G4endl;
*/
  return result;
}