#include <G4NeutronHPFissionData.hh>

Inheritance diagram for G4NeutronHPFissionData:

Public Member Functions
	G4NeutronHPFissionData ()

	~G4NeutronHPFissionData ()

G4bool	IsIsoApplicable (const G4DynamicParticle , G4int, G4int, const G4Element , const G4Material *)

G4double	GetIsoCrossSection (const G4DynamicParticle , G4int, G4int, const G4Isotope , const G4Element , const G4Material )

G4double	GetCrossSection (const G4DynamicParticle , const G4Element , G4double aT)

void	BuildPhysicsTable (const G4ParticleDefinition &)

void	DumpPhysicsTable (const G4ParticleDefinition &)

Public Member Functions inherited from G4VCrossSectionDataSet
	G4VCrossSectionDataSet (const G4String &nam="")

virtual	~G4VCrossSectionDataSet ()

virtual G4bool	IsElementApplicable (const G4DynamicParticle , G4int Z, const G4Material mat=0)

virtual G4bool	IsIsoApplicable (const G4DynamicParticle , G4int Z, G4int A, const G4Element elm=0, const G4Material *mat=0)

G4double	GetCrossSection (const G4DynamicParticle , const G4Element , const G4Material *mat=0)

G4double	ComputeCrossSection (const G4DynamicParticle , const G4Element , const G4Material *mat=0)

virtual G4double	GetElementCrossSection (const G4DynamicParticle , G4int Z, const G4Material mat=0)

virtual G4double	GetIsoCrossSection (const G4DynamicParticle , G4int Z, G4int A, const G4Isotope iso=0, const G4Element elm=0, const G4Material mat=0)

virtual G4Isotope *	SelectIsotope (const G4Element *, G4double kinEnergy)

virtual void	BuildPhysicsTable (const G4ParticleDefinition &)

virtual void	DumpPhysicsTable (const G4ParticleDefinition &)

virtual void	CrossSectionDescription (std::ostream &) const

void	SetVerboseLevel (G4int value)

G4double	GetMinKinEnergy () const

void	SetMinKinEnergy (G4double value)

G4double	GetMaxKinEnergy () const

void	SetMaxKinEnergy (G4double value)

const G4String &	GetName () const

Additional Inherited Members
Protected Member Functions inherited from G4VCrossSectionDataSet
void	SetName (const G4String &)

Protected Attributes inherited from G4VCrossSectionDataSet
G4int	verboseLevel

Detailed Description

Definition at line 48 of file G4NeutronHPFissionData.hh.

Constructor & Destructor Documentation

◆ G4NeutronHPFissionData()

G4NeutronHPFissionData::G4NeutronHPFissionData ( )

Definition at line 42 of file G4NeutronHPFissionData.cc.

: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::~G4NeutronHPFissionData ( )

Definition at line 57 of file G4NeutronHPFissionData.cc.

{
   if ( theCrossSections != NULL ) theCrossSections->clearAndDestroy();
   delete theCrossSections;
}

Member Function Documentation

◆ BuildPhysicsTable()

void G4NeutronHPFissionData::BuildPhysicsTable ( const G4ParticleDefinition & aP )

virtual

Reimplemented from G4VCrossSectionDataSet.

Definition at line 102 of file G4NeutronHPFissionData.cc.

{
  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);
  }
}

Referenced by G4NeutronHPFissionData().

◆ DumpPhysicsTable()

void G4NeutronHPFissionData::DumpPhysicsTable ( const G4ParticleDefinition & aP )

virtual

Reimplemented from G4VCrossSectionDataSet.

Definition at line 126 of file G4NeutronHPFissionData.cc.

{
  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;
}

◆ GetCrossSection()

G4double G4NeutronHPFissionData::GetCrossSection	(	const G4DynamicParticle *	aP,
		const G4Element *	anE,
		G4double	aT
	)

Definition at line 184 of file G4NeutronHPFissionData.cc.

{
  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;
}

Referenced by GetIsoCrossSection().

◆ GetIsoCrossSection()

G4double G4NeutronHPFissionData::GetIsoCrossSection	(	const G4DynamicParticle *	dp,
		G4int	,
		G4int	,
		const G4Isotope *	,
		const G4Element *	element,
		const G4Material *	material
	)

virtual

Reimplemented from G4VCrossSectionDataSet.

Definition at line 76 of file G4NeutronHPFissionData.cc.

{
   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;
}

◆ IsIsoApplicable()

G4bool G4NeutronHPFissionData::IsIsoApplicable	(	const G4DynamicParticle *	dp,
		G4int	,
		G4int	,
		const G4Element *	,
		const G4Material *
	)

virtual

Reimplemented from G4VCrossSectionDataSet.

Definition at line 63 of file G4NeutronHPFissionData.cc.

{
   G4double eKin = dp->GetKineticEnergy();
   if ( eKin > GetMaxKinEnergy() 
     || eKin < GetMinKinEnergy() 
     || dp->GetDefinition() != G4Neutron::Neutron() ) return false;                                   
 
   return true;
}

The documentation for this class was generated from the following files:

Public Member Functions

Additional Inherited Members

Detailed Description

Constructor & Destructor Documentation

◆ G4NeutronHPFissionData()

◆ ~G4NeutronHPFissionData()

Member Function Documentation

◆ BuildPhysicsTable()

◆ DumpPhysicsTable()

◆ GetCrossSection()

◆ GetIsoCrossSection()

◆ IsIsoApplicable()