NucleusMCRecord Class Reference

A NucleusMCRecord allows to record data for writing &reading reaction rates tallies. More...

#include <NucleusMCRecord.hxx>

Public Member Functions
Constructor &destructor
	NucleusMCRecord ()
	normal contructor
	NucleusMCRecord (const NucleusMCRecord &n)
	Copy constructor.
	~NucleusMCRecord ()
	Destructor.
Building bins &Co. methods
void	SetTallyNumber (int tallynum)
int	GetTallyNumber ()
void	AddCellnTallyBin (int CellNum, int BinIdx)
vector< int >	AddMultiplicatorBinIndex (int &FMBinIdx, Nucleus *nuc)
	Set Multiplicator tally bin index for reaction rates.
vector< int > &	GetMultiplicatorBinIndex ()
void	SetTotalXSMultiplicatorBinIndex (int FMbin)
int	GetTotalXSMultiplicatorBinIndex ()

Miscellaneous methods
int	fTallyNum
	Tally Number for reaction rates.
int	fFMTotalBinIdx
	Multiplicator bin index for the total reaction rate.
vector< int >	fFMBinIdx
	Multiplicator bin index for reaction rate.
vector< pair< int, int > >	fCellnTallyBin
	pair of (Cell number, Tally cell bin index)
int	GetNumberOfCellBin ()
int	GetNumberOfMultiplicatorBin ()
int	GetCellNumber (int i)
int	GetTallyBinIndex (int i)
vector< pair< int, int > > &	GetCellnTallyBin ()

Detailed Description

A NucleusMCRecord allows to record data for writing &reading reaction rates tallies.

One Nucleus (of one perturbative material) is.created for each temperature. In MCNP, one use 1 tally/temperature for all cells at this temperature. But for Serpent, because tally (detector) normalization is only possible with a unique volume, one use 1 tally/cell, independantly from the temperature. This lead for MCNP to 1 tally with lot of cell bins and their associated multiplicator bins for reaction rates and for Serpent, to lot of tallies with 1 cell bin (and their associated multiplicator bins for reaction rates).

This class allows to keep the correct way of storing data in order to retreive them when filling cross sections and reaction rates of the nucleus.

Author

PTO

Version

1.0

Constructor & Destructor Documentation

NucleusMCRecord() [1/2]

NucleusMCRecord::NucleusMCRecord ( )

default

normal contructor

NucleusMCRecord() [2/2]

NucleusMCRecord::NucleusMCRecord

(

const NucleusMCRecord &

n

)

Copy constructor.

~NucleusMCRecord()

NucleusMCRecord::~NucleusMCRecord

(

)

Destructor.

Member Function Documentation

AddCellnTallyBin()

void NucleusMCRecord::AddCellnTallyBin	(	int	CellNum,
		int	BinIdx
	)

Create, if necessary, a new pair of (Cell Number, Cell bin index)

AddMultiplicatorBinIndex()

vector< int > NucleusMCRecord::AddMultiplicatorBinIndex	(	int &	FMBinIdx,
		Nucleus *	nuc
	)

Set Multiplicator tally bin index for reaction rates.

Fills Multiplicator Tally bin index vector starting at bin "FMBinIdx" to "FMBinIdx+nb of reactions+1" (the last one is for total reaction rates). Output: FMBinIdx is set to FMBinIdx+(nb of reactions)+1 and a vector of XS codes (ENDF type) is given

Parameters

FMBinIdx	: input: starting bin for the first reaction, ouput: FMBinIdx+last bin for the last reaction+1
nuc	: the "calling" Nucleus

GetCellnTallyBin()

vector< pair< int, int > > & NucleusMCRecord::GetCellnTallyBin ( )

inline

< return the pair vector of (Cell Number, Cell bin index)

GetCellNumber()

int NucleusMCRecord::GetCellNumber ( int  i )

inline

< return the Cell number in the ith tally bin

GetMultiplicatorBinIndex()

vector< int > & NucleusMCRecord::GetMultiplicatorBinIndex ( )

inline

GetNumberOfCellBin()

int NucleusMCRecord::GetNumberOfCellBin ( )

inline

GetNumberOfMultiplicatorBin()

int NucleusMCRecord::GetNumberOfMultiplicatorBin ( )

inline

GetTallyBinIndex()

int NucleusMCRecord::GetTallyBinIndex ( int  i )

inline

< return the position index of the ith Cell number in the tally

GetTallyNumber()

int NucleusMCRecord::GetTallyNumber ( )

inline

< return the tally multiplicator number

GetTotalXSMultiplicatorBinIndex()

int NucleusMCRecord::GetTotalXSMultiplicatorBinIndex ( )

inline

< return reaction rate bin in a tally

SetTallyNumber()

void NucleusMCRecord::SetTallyNumber ( int  tallynum )

inline

< Set the tally multiplicator number

SetTotalXSMultiplicatorBinIndex()

void NucleusMCRecord::SetTotalXSMultiplicatorBinIndex ( int  FMbin )

inline

< set total reaction rate bin in a tally

Member Data Documentation

fCellnTallyBin

vector< pair < int, int > > NucleusMCRecord::fCellnTallyBin

private

pair of (Cell number, Tally cell bin index)

fFMBinIdx

vector< int > NucleusMCRecord::fFMBinIdx

private

Multiplicator bin index for reaction rate.

fFMTotalBinIdx

int NucleusMCRecord::fFMTotalBinIdx

private

Multiplicator bin index for the total reaction rate.

fTallyNum

int NucleusMCRecord::fTallyNum

private

Tally Number for reaction rates.

---

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

• /gpr/meplan/SMURE/source/include/NucleusMCRecord.hxx
• /gpr/meplan/SMURE/source/src/NucleusMCRecord.cxx