Allows to read XS file in the MCNP ACE format. More...

#include <ReadXSFile.hxx>

Public Member Functions
	ReadXSFile (ifstream *inputfile, int start_record, int table_length, int record_length, int nrecord_per_entry, string FN)

	ReadXSFile (ifstream *inputfile, int start_record, int table_length, string FN)

	ReadXSFile (const ReadXSFile &XSF)
	copy constructor More...

	~ReadXSFile ()
	destructor More...

Real	GetInterpolXS (int MT, Real E)
	returns linear in (log-log) interpol of XS for reaction MT at energy E More...

Real	GetXS (int MT, Real E)
	returns XS for reaction MT at energy E More...

Real	GetXS (int MT, int BinE)
	returns XS for reaction MT at energy GetEnergy(BinE) More...

double	SumXS (int MT)
	returns $\int\sigma^{MT}(E)d\log E$ More...

Real *	GetEnergy ()
	returns the Energy array where XS are defined More...

Real	GetEnergy (int i)
	returns the ith energy of the Energy array More...

int	GetNEnergy ()
	returns the size of the Energy array More...

int	GetXSMinEnergyBin (int MT)
	returns the lower energy bin for the XS(MT) More...

int	GetXSMaxEnergyBin (int MT)
	returns the upper energy bin for the XS(MT) More...

int	FindEnergyBin (double E, int N, float *Ephi)
	returns the bin for energy E in array Ephi More...

int	FindEnergyBin (Real E, int N, Real *Earray)
	returns the bin for energy E in array Earray More...

int	FindEnergyBin (Real E)
	returns the bin for energy E More...

bool	IsXSFound ()
	whether a XS is found in the file More...

Real *	GetTotalNuBar (int &NE, Real *&E, bool &Todelete)
	returns the total mean nu (fission neutron yield) More...

Real	GetTotalInterpolateNuBar (Real E)
	returns the total mean nu at E (fission neutron yield) More...

Real *	GetPromptNuBar (int &NE, Real *&E)
	returns the prompt mean nu (fission neutron yield) More...

ValErr_t	SigmaPhi (int N, vector< ValErr_t > &Phi, float *Ephi, int MT)
	return $\int \phi \sigma^{MT}(E)dE$ More...

ValErr_t	NuSigmaFisPhi (int N, vector< ValErr_t > &Phi, float *Ephi)
	return $\int \phi \nu(E)\sigma^{f}(E)dE$ More...

Private Member Functions
void	ReadNXS ()
	read the NXS array (Binary) More...

void	ReadJXS ()
	read the JXS array (Binary) More...

void	ReadAsciiNXS ()
	read the NXS array (Ascii) More...

void	ReadAsciiJXS ()
	read the JXS array (Ascii) More...

void	AffectPointer ()
	decomposed all global arrays in user understandable one More...

Real *	GetXS (int MT)
	returns the XS array of reaction MT More...

Real	GetTotalFissionXS (Real E)
	returns total fission XS (prefer GetFissionXS()) More...

Real	GetFissionXS (int binE)
	returns total fission XS More...

void	XSFound ()
	XS is found. More...

int	GetXSMinMaxEnergyBin (int MT, int min)
	find the lower(min=0) or upper (min=1) Energy bin for reaction MT More...

Private Attributes
ifstream *	OriginalFile
	Original MCNP ENDF Data File. More...

int	fNXS [16]
	Array of NXS (size, ...) More...

int	fJXS [32]
	Array of JXS (address of XS) More...

Real *	fReactionType
	Array [fNReaction] of ENDF reaction type. More...

int	fNReaction
	Number of reaction (ONLY neutrons) More...

Real *	fEnergy
	Energy grid [0..fNEnergy-1]. More...

int	fNEnergy
	Number of Energy point. More...

Real *	fTotalXS
	Total cross-section [0..fNEnergy-1]. More...

Real *	fAbsorptionXS
	Total Absorption cross-section [0..fNEnergy-1]. More...

Real *	fElasticXS
	Elastic scattering cross-section [0..fNEnergy-1]. More...

Real **	fXS
	Cross-section array[fNReaction][...]. More...

Real *	XXS
	XXS array (all the 2nd block of the Library) More...

int	fNXXS
	Size of this array. More...

Real *	fLocXS
	Address number for some reaction cross-sections. More...

bool	fXSFound
	Wether a XS is found or not. More...

Detailed Description

Allows to read XS file in the MCNP ACE format.

All that numbers needed to read XS file are given in the xsdir. WARNING: UNITS ARE MCNP UNITS, i.e. [ENERGY]=MeV and [XS]=barns WARNING: For binary data:

- use the correct compilation flag (mcnp4 or mcnp5)

the binary data MUST have been generated with a makexsf compiled with the "-assume byterecl" flag of Intel Fortran

Author: PTO

Version: 0.9

Constructor & Destructor Documentation

ReadXSFile::ReadXSFile	(	ifstream *	inputfile,
		int	start_record,
		int	table_length,
		int	record_length,
		int	nrecord_per_entry,
		string	FN
	)

Normal Constructor for Binary Cross-section libraries. Read the XS file.

Parameters

inputfile	: the XS file where to find data
start_record	: the address of the first record of the first block in inputfile
table_length	: the table length of the 2nd block
record_length	: the record length
nrecord_per_entry	: the number of record per entries
FN	: Base File Name (only for output error)

ReadXSFile::ReadXSFile	(	ifstream *	inputfile,
		int	start_record,
		int	table_length,
		string	FN
	)

Normal Constructor for ASCII Cross-section libraries. Read the XS file.

Parameters

inputfile	: the XS file where to find data
start_record	: the address (line number) of the first record of the first block in inputfile
table_length	: the table length of the 2nd block
FN	: Base File Name (only for output error)

ReadXSFile::ReadXSFile ( const ReadXSFile & XSF )

copy constructor

ReadXSFile::~ReadXSFile ( )

destructor

Member Function Documentation

void ReadXSFile::AffectPointer ( )

private

decomposed all global arrays in user understandable one

int ReadXSFile::FindEnergyBin	(	double	E,
		int	N,
		float *	Ephi
	)

returns the bin for energy E in array Ephi

int ReadXSFile::FindEnergyBin	(	Real	E,
		int	N,
		Real *	Earray
	)

returns the bin for energy E in array Earray

int ReadXSFile::FindEnergyBin ( Real E )

returns the bin for energy E

Real * ReadXSFile::GetEnergy ( )

returns the Energy array where XS are defined

Real ReadXSFile::GetEnergy ( int i )

returns the ith energy of the Energy array

Real ReadXSFile::GetFissionXS ( int binE )

private

returns total fission XS

Real ReadXSFile::GetInterpolXS	(	int	MT,
		Real	E
	)

returns linear in (log-log) interpol of XS for reaction MT at energy E

int ReadXSFile::GetNEnergy ( )

inline

returns the size of the Energy array

Real * ReadXSFile::GetPromptNuBar	(	int &	NE,
		Real *&	E
	)

returns the prompt mean nu (fission neutron yield)

Real ReadXSFile::GetTotalFissionXS ( Real E )

private

returns total fission XS (prefer GetFissionXS())

Real ReadXSFile::GetTotalInterpolateNuBar ( Real E )

returns the total mean nu at E (fission neutron yield)

Real * ReadXSFile::GetTotalNuBar	(	int &	NE,
		Real *&	E,
		bool &	Todelete
	)

returns the total mean nu (fission neutron yield)

Real ReadXSFile::GetXS	(	int	MT,
		Real	E
	)

returns XS for reaction MT at energy E

Real ReadXSFile::GetXS	(	int	MT,
		int	BinE
	)

returns XS for reaction MT at energy GetEnergy(BinE)

Real * ReadXSFile::GetXS ( int MT )

private

returns the XS array of reaction MT

int ReadXSFile::GetXSMaxEnergyBin ( int MT )

returns the upper energy bin for the XS(MT)

int ReadXSFile::GetXSMinEnergyBin ( int MT )

returns the lower energy bin for the XS(MT)

int ReadXSFile::GetXSMinMaxEnergyBin	(	int	MT,
		int	min
	)

private

find the lower(min=0) or upper (min=1) Energy bin for reaction MT

bool ReadXSFile::IsXSFound ( )

inline

whether a XS is found in the file

ValErr_t ReadXSFile::NuSigmaFisPhi	(	int	N,
		vector< ValErr_t > &	Phi,
		float *	Ephi
	)

return $\int \phi \nu(E)\sigma^{f}(E)dE$

void ReadXSFile::ReadAsciiJXS ( )

private

read the JXS array (Ascii)

void ReadXSFile::ReadAsciiNXS ( )

private

read the NXS array (Ascii)

void ReadXSFile::ReadJXS ( )

private

read the JXS array (Binary)

void ReadXSFile::ReadNXS ( )

private

read the NXS array (Binary)

ValErr_t ReadXSFile::SigmaPhi	(	int	N,
		vector< ValErr_t > &	Phi,
		float *	Ephi,
		int	MT
	)

return $\int \phi \sigma^{MT}(E)dE$

double ReadXSFile::SumXS ( int MT )

returns $\int\sigma^{MT}(E)d\log E$

void ReadXSFile::XSFound ( )

inlineprivate

XS is found.

Member Data Documentation

Real* ReadXSFile::fAbsorptionXS

private

Total Absorption cross-section [0..fNEnergy-1].

Real* ReadXSFile::fElasticXS

private

Elastic scattering cross-section [0..fNEnergy-1].

Real* ReadXSFile::fEnergy

private

Energy grid [0..fNEnergy-1].

int ReadXSFile::fJXS[32]

private

Array of JXS (address of XS)

Real* ReadXSFile::fLocXS

private

Address number for some reaction cross-sections.

int ReadXSFile::fNEnergy

private

Number of Energy point.

int ReadXSFile::fNReaction

private

Number of reaction (ONLY neutrons)

int ReadXSFile::fNXS[16]

private

Array of NXS (size, ...)

int ReadXSFile::fNXXS

private

Size of this array.

Real* ReadXSFile::fReactionType

private

Array [fNReaction] of ENDF reaction type.

Real* ReadXSFile::fTotalXS

private

Total cross-section [0..fNEnergy-1].

Real** ReadXSFile::fXS

private

Cross-section array[fNReaction][...].

bool ReadXSFile::fXSFound

private

Wether a XS is found or not.

ifstream* ReadXSFile::OriginalFile

private

Original MCNP ENDF Data File.

Real* ReadXSFile::XXS

private

XXS array (all the 2nd block of the Library)

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

/home/meplan/MURE/source/include/ReadXSFile.hxx
/home/meplan/MURE/source/src/ReadXSFile.cxx

Public Member Functions

Private Member Functions

Private Attributes

Detailed Description

Constructor & Destructor Documentation

Member Function Documentation

Member Data Documentation