G4NeutronHPFissionData.cc

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//
// neutron_hp -- source file
// J.P. Wellisch, Nov-1996
// A prototype of the low energy neutron transport model.
//
// 070618 fix memory leaking by T. Koi
// 071002 enable cross section dump by T. Koi
// 081024 G4NucleiPropertiesTable:: to G4NucleiProperties::
// 081124 Protect invalid read which caused run time errors by T. Koi
// 100729 Add safty for 0 lenght cross sections by T. Koi
 
#include "G4NeutronHPFissionData.hh"
#include "G4SystemOfUnits.hh"
#include "G4Neutron.hh"
#include "G4ElementTable.hh"
#include "G4NeutronHPData.hh"
 
G4NeutronHPFissionData::G4NeutronHPFissionData()
:G4VCrossSectionDataSet("NeutronHPFissionXS")
{
   SetMinKinEnergy( 0*MeV );                                   
   SetMaxKinEnergy( 20*MeV );                                   
 
   ke_cache = 0.0;
   xs_cache = 0.0;
   element_cache = NULL;
   material_cache = NULL;
 
   theCrossSections = 0;
   BuildPhysicsTable(*G4Neutron::Neutron());
}
   
G4NeutronHPFissionData::~G4NeutronHPFissionData()
{
   if ( theCrossSections != NULL ) theCrossSections->clearAndDestroy();
   delete theCrossSections;
}
 
G4bool G4NeutronHPFissionData::IsIsoApplicable( const G4DynamicParticle* dp , 
                                                G4int /*Z*/ , G4int /*A*/ ,
                                                const G4Element* /*elm*/ ,
                                                const G4Material* /*mat*/ )
{
   G4double eKin = dp->GetKineticEnergy();
   if ( eKin > GetMaxKinEnergy() 
     || eKin < GetMinKinEnergy() 
     || dp->GetDefinition() != G4Neutron::Neutron() ) return false;                                   
 
   return true;
}
 
G4double G4NeutronHPFissionData::GetIsoCrossSection( const G4DynamicParticle* dp ,
                                   G4int /*Z*/ , G4int /*A*/ ,
                                   const G4Isotope* /*iso*/  ,
                                   const G4Element* element ,
                                   const G4Material* material )
{
   if ( dp->GetKineticEnergy() == ke_cache && element == element_cache &&  material == material_cache ) return xs_cache;
 
   ke_cache = dp->GetKineticEnergy();
   element_cache = element;
   material_cache = material;
   G4double xs = GetCrossSection( dp , element , material->GetTemperature() );
   xs_cache = xs;
   return xs;
}
 
/*
G4bool G4NeutronHPFissionData::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;
}
*/
 
void G4NeutronHPFissionData::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 == NULL ) theCrossSections = new G4PhysicsTable( numberOfElements );
   if ( theCrossSections == NULL ) 
      theCrossSections = new G4PhysicsTable( numberOfElements );
   else
      theCrossSections->clearAndDestroy();
 
  // 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 G4NeutronHPFissionData::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 << "Fission 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;
 
      if ( (*((*theCrossSections)(i))).GetVectorLength() == 0 ) 
      {
         G4cout << "The cross-section data of the fission of this element is not available." << G4endl; 
         G4cout << G4endl; 
         continue;
      }
 
      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 << "G4NeutronHPFissionData::DumpPhysicsTable still to be implemented"<<G4endl;
}
 
#include "G4NucleiProperties.hh"
 
G4double G4NeutronHPFissionData::
GetCrossSection(const G4DynamicParticle* aP, const G4Element*anE, G4double aT)
{
  G4double result = 0;
  if(anE->GetZ()<90) return result;
  G4bool outOfRange;
  G4int index = anE->GetIndex();
 
// 100729 TK add safety
if ( ( ( *theCrossSections )( index ) )->GetVectorLength() == 0 ) return result;
 
  // prepare neutron
  G4double eKinetic = aP->GetKineticEnergy();
  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 = ( G4NucleiProperties::GetNuclearMass( static_cast<G4int>(theA+eps) , static_cast<G4int>(theZ+eps) )
         ) / G4Neutron::Neutron()->GetPDGMass();
  
  G4ReactionProduct boosted;
  G4double aXsection;
  
  // MC integration loop
  G4int counter = 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);
      // velocity correction.
      G4ThreeVector targetVelocity = 1./aThermalNuc.GetMass()*aThermalNuc.GetMomentum();
      aXsection *= (targetVelocity-neutronVelocity).mag()/neutronVMag;
      result += aXsection;
    }
    size += size;
  }
  result /= counter;
  return result;
}