MCNPSource Class Reference

Define a MCNP Source. More...

#include <MCNPSource.hxx>

Inheritance diagram for MCNPSource:

Public Member Functions
	MCNPSource (double NPS=10000)
	Normal Constructor.
	MCNPSource (const MCNPSource &s)
	Copy Constructor.
MCSource *	Clone () override
	Clone method.
	~MCNPSource () override
	destructor
void	UsePreviousRunSource (string FirstSource="") override
	use a previous kcode source for mcnp.
void	SetEnergy (string E)
void	SetEXT (string EXT)
void	SetEXT (double ext)
void	SetCEL (int cel)
void	SetVEC (double i=0, double j=0, double k=0)
	Set the reference vector for DIR.
void	SetVEC (string vec)
	set reference vector in a string as "i j k"
void	SetAXS (double i=0, double j=0, double k=0)
	Set the reference vector for EXT and RAD.
void	SetAXS (string axs)
void	SetX (string x)
void	SetY (string y)
void	SetZ (string z)
void	AddBias (string bias)
	add a bias to the bias vector
void	SetDirection (string dir)
void	SetRadius (string rad)
void	SetParticleType (int particle)
int	GetParticleType ()
void	SetParticleDistribution (string ParticleDistribution)
void	SetDistribution (string D)
void	SetKSRC ()
void	SetSSR ()
bool	GetSSR ()
void	AddPosition (double *pos)
	Add a position to the KSRC position vector (in m)
void	AddPosition (double x, double y, double z)
	Add a position to the KSRC position vector (in m)
void	SetKSRCPosition (int i, double *pos)
string	Print () override
	Print the MCNP source (into MNCP input file).
void	AddTubeSource (MathTube *tube, string TubeParticleEnergy="1e6")
void	AddTubeSource (MathTube *tube, Spectrum *spectrum)
void	UseThisEnergyDistribution (Spectrum *spectrum, int SourceDistributionNum=800)
string	PrintTubeSource ()
	Print a Tube Source in MCNP.
void	SetSurfaceNumber (int num)
void	SetEnergy (double E=2.5e6)
	Set the energy for a point source (in eV)
Public Member Functions inherited from MCSource
	MCSource (double NPS=10000)
	Normal Constructor.
	MCSource (const MCSource &s)
	Copy Constructor.
virtual MCSource *	Clone ()=0
	Clone method.
virtual	~MCSource ()
	destructor
void	SetNPS (double NPS=10000)
double	GetNPS ()
void	SetEnergy (double E=2.5e6)
	Set the energy for a point source (in eV)
void	SetPosition (double *pos=nullptr)
	set the position of a point source (in m)
void	SetPosition (double x=0, double y=0, double z=0)
	set the position of a point source (in m)
double *	GetPosition ()
virtual void	SetSurface (Shape_ptr TheShape)
	set the Surface number for a surface source.
void	SetNormal (double nrm)
void	SetWeight (double wgt)
void	SetExtern (bool state=true)
void	SetKcode (int ActiveCycle=100, int InactiveCycle=10, double ExpectedKeff=1.)
bool	GetKcode ()
int	GetNActiveCycle ()
int	GetNInactiveCycle ()
virtual string	Print ()=0
	Print the MC source (into MC transport code input file).
virtual void	UsePreviousRunSource (string FirstSource="")=0
	use a previous kcode source for mcnp.
virtual bool	IsUsePrevSource ()
void	SetUsePrevSource (bool flag=true)
string	GetSourceFileName ()
void	SetSourceFileName (string name)
void	SetOriginalSourceFileName (string name)
string	GetOriginalSourceFileName ()
bool	IsStochasticVolumeSource ()
	True if this is a Stochastic Volume Source run.
void	SetStochasticVolumeSourceShape (Shape_ptr TheShape)
	Set the shape of the outer most sphere for Stochastic Volume run.
Shape_ptr	GetStochasticVolumeSourceShape ()
	get the source sphere for Stochastic Volume Source run

Private Attributes
int	fParticleType
	particle type for the source (1=neutron)
int	fSurfaceNumber
	particle type for the source (1=neutron)
string	fDirection
	direction bias
string	fRadius
	direction bias
string	fDistribution
	source distribution (use with bias)
string	fEXT
	Cell case:distance from POS along AXS Surface Case:cosine of angle from AXS.
string	X
string	Y
string	Z
vector< string >	fVEC
	Reference vector for DIR.
vector< string >	fAXS
	Reference vector for ext and rad.
vector< string >	fBias
	vector of bias
int	fCEL
bool	fKSRC
	whether or not a KSRC source is wanted
bool	fSSR
	whether or not a surface source read is wanted
string	fParticleDistribution
	if not only one particle
vector< double * >	fKSRCposition
	KSRC position vector.
vector< MathTube * >	fSourceTube
	vector of Tube for <> sources
vector< string >	fTubeParticleEnergy
	vector of "energies" of each source tube (double or distribution)
vector< Spectrum * >	fTubeParticleSpectrum
	vector of energy spectrum if the source uses Spectrum
vector< double >	fSourceTubeRelIntensities
vector< Cell * >	fTubeCell

Additional Inherited Members
Protected Attributes inherited from MCSource
double	fNPS
	number of source particles
string	fEnergy
	Energy of the Source (either a number or a bias)
double *	fPosition
	Position of the point Source (if it is the case)
Shape_ptr	fSurfaceShape
	Surface Shape for surface source (if it is the case)
double	fNormal
	Normal direction (inward or outward) for particle source.
double	fWeight
	weight of the source
bool	fExtern
	whether the source is extern or defined in MCNP file
bool	fKcode
	whether or not a KCODE is wanted
int	fActiveCycle
	number of active cycles in KCODE
int	fInactiveCycle
	number of inactive cycles in KCODE
double	fKeff
	expected Keff in KCODE
string	fSourceFile
	Name of the next source if using file source.
string	fOriginalSourceFile
	Name of the Original source file.
bool	fUsePrevSource
	Whether MURE must use the preivous run source or not.
bool	fStochasticVolumeSource
Shape_ptr	fStochasticVolumeSourceShape

Detailed Description

Define a MCNP Source.

This source has to be added to the global gMURE pointer.

See also

MURE::SetSource

Author

PTO

Version

2.0

Constructor & Destructor Documentation

MCNPSource() [1/2]

MCNPSource::MCNPSource

(

double

NPS = 10000

)

Normal Constructor.

Parameters

NPS	: number of source particles (default=10 000)

MCNPSource() [2/2]

MCNPSource::MCNPSource

(

const MCNPSource &

s

)

Copy Constructor.

~MCNPSource()

MCNPSource::~MCNPSource ( )

override

destructor

Member Function Documentation

AddBias()

void MCNPSource::AddBias

(

string

bias

)

add a bias to the bias vector

AddPosition() [1/2]

void MCNPSource::AddPosition

(

double *

pos

)

Add a position to the KSRC position vector (in m)

AddPosition() [2/2]

void MCNPSource::AddPosition	(	double	x,
		double	y,
		double	z
	)

Add a position to the KSRC position vector (in m)

AddTubeSource() [1/2]

void MCNPSource::AddTubeSource	(	MathTube *	tube,
		Spectrum *	spectrum
	)

Add a isotropic volumetric Tube source. It allows to define an uniform volumic source in Tube(s).Usefull to define sources in an assembly. The first use was to calculated gamma bremmstralung from Beta Decay.

You CANNOT use in the same code AddTubeSource(MathTube*, string) and AddTubeSource(MathTube*, Spectrum*).

Parameters

tube	: the Tube used to define the source shape
spectrum	: must be either NeutronSpectrum,GammaSpectrum or BetaSpectrum to define the particle and it energy spectrum

AddTubeSource() [2/2]

void MCNPSource::AddTubeSource	(	MathTube *	tube,
		string	TubeParticleEnergy = "1e6"
	)

Add a isotropic volumetric Tube source. It allows to define an uniform volumic source in Tube(s).Usefull to define sources in an assembly. The first use was to calculated gamma bremmstralung from Beta Decay.

You CANNOT use in the same code AddTubeSource(MathTube*, string) and AddTubeSource(MathTube*, Spectrum*).

Parameters

tube	: the Tube used to define the source shape
TubeParticleEnergy	: a string containing either a double for mono-energy neutrons, either a source distribution "Dxxx" where xxx is an int. In that case, the user MUST provide via MCNPSource::AddBias() the description of this distribution.

Clone()

MCSource * MCNPSource::Clone ( )

inlineoverridevirtual

Clone method.

< Clone method

Implements MCSource.

GetParticleType()

int MCNPSource::GetParticleType ( )

inline

< get the Particletype (1=n,9=H,...)

GetSSR()

bool MCNPSource::GetSSR ( )

inline

< Surface Source Reading

Print()

string MCNPSource::Print ( )

overridevirtual

Print the MCNP source (into MNCP input file).

Implements MCSource.

PrintTubeSource()

string MCNPSource::PrintTubeSource

(

)

Print a Tube Source in MCNP.

SetAXS() [1/2]

void MCNPSource::SetAXS	(	double	i = 0,
		double	j = 0,
		double	k = 0
	)

Set the reference vector for EXT and RAD.

SetAXS() [2/2]

void MCNPSource::SetAXS

(

string

axs

)

SetCEL()

void MCNPSource::SetCEL

(

int

cel

)

SetDirection()

void MCNPSource::SetDirection ( string  dir )

inline

< set the direction bias

SetDistribution()

void MCNPSource::SetDistribution ( string  D )

inline

Set the source distribution. In MCNP, one can define source with distributions ; each distribution is associated with source probability and/or source information. This probabilities and information have to be defined in MCNPSource::AddBias(). For example:

MCNPSource s;
s.SetDistribution("RAD=D1 EXT =D2");
s.AddBias("SI1 1 2"); //radial extension (from r=1cm to r=2cm)
s.AddBias("SI2 -10 10");//axial extension (from z=-10cm to z=10cm)

Rem: one can specify also any cards of a SDEF line (such as AXS x y z, ...).

Parameters

D	: the source distribution.

SetEnergy() [1/2]

void MCSource::SetEnergy

(

double

E = 2.5e6

)

Set the energy for a point source (in eV)

SetEnergy() [2/2]

void MCNPSource::SetEnergy ( string  E )

inline

< Set the source energy (using bias)

SetEXT() [1/2]

void MCNPSource::SetEXT

(

double

ext

)

SetEXT() [2/2]

void MCNPSource::SetEXT ( string  EXT )

inline

< See fEXT description

SetKSRC()

void MCNPSource::SetKSRC ( )

inline

Set KSRC source for MCNP. It allows to suppress SDEF card and specify multipoint source position. See MCNPSource::AddPosition()

SetKSRCPosition()

void MCNPSource::SetKSRCPosition ( int  i, double *  pos  )

inline

< Allow to modify a KSRC point source position

SetParticleDistribution()

void MCNPSource::SetParticleDistribution ( string  ParticleDistribution )

inline

< set the Particle Distibution if more than one particle type

SetParticleType()

void MCNPSource::SetParticleType ( int  particle )

inline

< set the Particletype (1=n,9=H,...)

SetRadius()

void MCNPSource::SetRadius ( string  rad )

inline

< set the Radius bias

SetSSR()

void MCNPSource::SetSSR ( )

inline

< Surface Source Reading

SetSurfaceNumber()

void MCNPSource::SetSurfaceNumber ( int  num )

inline

< Set the surface number

SetVEC() [1/2]

void MCNPSource::SetVEC	(	double	i = 0,
		double	j = 0,
		double	k = 0
	)

Set the reference vector for DIR.

SetVEC() [2/2]

void MCNPSource::SetVEC

(

string

vec

)

set reference vector in a string as "i j k"

SetX()

void MCNPSource::SetX ( string  x )

inline

SetY()

void MCNPSource::SetY ( string  y )

inline

SetZ()

void MCNPSource::SetZ ( string  z )

inline

UsePreviousRunSource()

void MCNPSource::UsePreviousRunSource ( string  FirstSource = "" )

overridevirtual

use a previous kcode source for mcnp.

Tells MCSource to use for the next MC run the fission source obtained from a previous critical run. In an evolution, each MC step is done using the source from the previous MC step (or the input "s" file provide by the user). This can be used to reduce inactive cycle in critical calculation, starting from an already converge fission source.

Parameters

FirstSource

: name of the first source to use. If not specified, creates a default source.

Implements MCSource.

UseThisEnergyDistribution()

void MCNPSource::UseThisEnergyDistribution	(	Spectrum *	spectrum,
		int	SourceDistributionNum = 800
	)

Use a spectrum as an energy distribution. It allows to use your spectrum object (BetaSpectrum,GammaSpectrum,or NeutronSpectrum) as a MCNP energy distribution

Parameters

spectrum	: must be either NeutronSpectrum,GammaSpectrum or BetaSpectrum
SourceDistributionNum	: the MCNP source distribution number used in D, SI,SP, ... cards

Member Data Documentation

fAXS

vector<string> MCNPSource::fAXS

private

Reference vector for ext and rad.

fBias

vector<string> MCNPSource::fBias

private

vector of bias

fCEL

int MCNPSource::fCEL

private

fDirection

string MCNPSource::fDirection

private

direction bias

fDistribution

string MCNPSource::fDistribution

private

source distribution (use with bias)

fEXT

string MCNPSource::fEXT

private

Cell case:distance from POS along AXS Surface Case:cosine of angle from AXS.

fKSRC

bool MCNPSource::fKSRC

private

whether or not a KSRC source is wanted

fKSRCposition

vector<double *> MCNPSource::fKSRCposition

private

KSRC position vector.

fParticleDistribution

string MCNPSource::fParticleDistribution

private

if not only one particle

fParticleType

int MCNPSource::fParticleType

private

particle type for the source (1=neutron)

fRadius

string MCNPSource::fRadius

private

direction bias

fSourceTube

vector<MathTube *> MCNPSource::fSourceTube

private

vector of Tube for <> sources

fSourceTubeRelIntensities

vector<double> MCNPSource::fSourceTubeRelIntensities

private

fSSR

bool MCNPSource::fSSR

private

whether or not a surface source read is wanted

fSurfaceNumber

int MCNPSource::fSurfaceNumber

private

particle type for the source (1=neutron)

fTubeCell

vector<Cell *> MCNPSource::fTubeCell

private

fTubeParticleEnergy

vector<string> MCNPSource::fTubeParticleEnergy

private

vector of "energies" of each source tube (double or distribution)

fTubeParticleSpectrum

vector<Spectrum *> MCNPSource::fTubeParticleSpectrum

private

vector of energy spectrum if the source uses Spectrum

fVEC

vector<string> MCNPSource::fVEC

private

Reference vector for DIR.

X

string MCNPSource::X

private

Y

string MCNPSource::Y

private

Z

string MCNPSource::Z

private

---

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

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