MCNPSource Class Reference

Define a MCNP Source. More...

#include <MCNPSource.hxx>

List of all members.

Public Member Functions
	MCNPSource (int NPS=10000)
	Normal Constructor.
	MCNPSource (const MCNPSource &s)
	Copy Constructor.
	~MCNPSource ()
	destructor
void	SetNPS (int NPS=10000)
	set the number of source particles (default=10 000).
int	GetNPS ()
	returns the number of source particles
void	SetEnergy (double E=2.5e6)
	Set the energy for a point source (in eV)
void	SetEnergy (string E)
	Set the source energy (using bias)
void	SetPosition (double *pos=0)
	set the position of a point source (SDEF) (in m)
void	SetPosition (double x=0, double y=0, double z=0)
	set the position of a point source (SDEF) (in m)
double *	GetPosition ()
	returns the position of a point source
void	SetSurface (int num)
	set the Surface number for a surface source.
void	SetSurface (Shape_ptr TheShape)
	set the Surface number for a surface source.
void	SetWeight (double wgt)
	set the Source particle weight
void	SetNormal (double nrm)
	Set the normal direction of source (inward or outward)
void	SetEXT (string EXT)
	See fEXT description.
void	SetEXT (double ext)
void	SetVEC (double i=0, double j=0, double k=0)
	Set the reference vector for DIR.
void	SetVEC (string vec)
void	SetAXS (double i=0, double j=0, double k=0)
	Set the reference vector for EXT and RAD.
void	SetAXS (string axs)
void	AddBias (string bias)
	add a bias to the bias vector
void	SetExtern (bool state=true)
void	SetDirection (string dir)
	set the direction bias
void	SetRadius (string rad)
	set the Radius bias
void	SetParticleType (int particle)
	set the Particletype (1=n,9=H,...)
int	GetParticleType ()
	get the Particletype (1=n,9=H,...)
void	SetParticleDistribution (string ParticleDistribution)
	set the Particle Distibution if more than one particle type
void	SetDistribution (string D)
void	SetKcode (int ActiveCycle=100, int InactiveCycle=10, double ExpectedKeff=1.)
bool	GetKcode ()
	returns true for KCODE calculation mode.
int	GetNActiveCycle ()
	Returns number of active Kcode cycles.
int	GetNInactiveCycle ()
	Returns number of inactive Kcode cycles.
void	SetKSRC ()
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)
	Allow to modify a KSRC point source position.
string	Print ()
	Print the MCNP source (into MNCP input file).
void	AddTubeSource (Tube *tube, string TubeParticleEnergy="1e6")
void	AddTubeSource (Tube *tube, Spectrum *spectrum)
void	UseThisEnergyDistribution (Spectrum *spectrum, int SourceDistributionNum=800)
string	PrintTubeSource ()
	Print a Tube Source in MCNP.
Private Attributes
int	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)
int	fSurface
	Surface number for surface 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
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.
vector< string >	fVEC
	Reference vector for DIR.
vector< string >	fAXS
	Reference vector for ext and rad.
vector< string >	fBias
	vector of bias
bool	fExtern
	whether the source is extern or defined in MCNP file
bool	fKcode
	whether or not a KCODE is wanted
bool	fKSRC
	whether or not a KSRC source is wanted
int	fActiveCycle
	number of active cycles in KCODE
int	fInactiveCycle
	number of inactive cycles in KCODE
double	fKeff
	expected Keff in KCODE
int	fParticleType
	particle type for the source (1=neutron)
string	fParticleDistribution
	if not only one particle
vector< double * >	fKSRCposition
	KSRC position vector.
vector< Tube * >	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

---

Detailed Description

Define a MCNP Source.

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

See also:

MURE::SetSource

Author:

PTO

Version:

1.0

---

Constructor & Destructor Documentation

MCNPSource::MCNPSource

(

int

NPS = 10000

)

Normal Constructor.

Parameters:

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

MCNPSource::MCNPSource

(

const MCNPSource &

s

)

Copy Constructor.

MCNPSource::~MCNPSource

(

)

destructor

---

Member Function Documentation

void MCNPSource::AddBias

(

string

bias

)

add a bias to the bias vector

void MCNPSource::AddPosition

(

double *

pos

)

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

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

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

void MCNPSource::AddTubeSource	(	Tube *	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(Tube*, string) and AddTubeSource(Tube*, 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.

void MCNPSource::AddTubeSource	(	Tube *	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(Tube*, string) and AddTubeSource(Tube*, 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

bool MCNPSource::GetKcode

(

)

[inline]

returns true for KCODE calculation mode.

int MCNPSource::GetNActiveCycle

(

)

[inline]

Returns number of active Kcode cycles.

int MCNPSource::GetNInactiveCycle

(

)

[inline]

Returns number of inactive Kcode cycles.

int MCNPSource::GetNPS

(

)

[inline]

returns the number of source particles

int MCNPSource::GetParticleType

(

)

[inline]

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

double* MCNPSource::GetPosition

(

)

[inline]

returns the position of a point source

string MCNPSource::Print

(

)

Print the MCNP source (into MNCP input file).

string MCNPSource::PrintTubeSource

(

)

Print a Tube Source in MCNP.

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

Set the reference vector for EXT and RAD.

void MCNPSource::SetAXS

(

string

axs

)

void MCNPSource::SetDirection

(

string

dir

)

[inline]

set the direction bias

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.

void MCNPSource::SetEnergy

(

double

E = 2.5e6

)

Set the energy for a point source (in eV)

void MCNPSource::SetEnergy

(

string

E

)

[inline]

Set the source energy (using bias)

void MCNPSource::SetEXT

(

string

EXT

)

[inline]

See fEXT description.

void MCNPSource::SetEXT

(

double

ext

)

void MCNPSource::SetExtern

(

bool

state = true

)

[inline]

Say whether the source is extern or defined in MCNP file. if set to "true", a external file is used (such as inps, source.mcnp, ...) else a SDEF card in used in the MCNP file. This can be used either in standard calculation either in KCODE calculation.

Parameters:

state

: if true an external source is used.

void MCNPSource::SetKcode	(	int	ActiveCycle = 100,
		int	InactiveCycle = 10,
		double	ExpectedKeff = 1.
	)

Set KCODE mode for MCNP.

Parameters:

ActiveCycle	: Number of active cycles for keff determination.
InactiveCycle	: Number of inactive cycles that are skipped for source stabilization
ExpectedKeff	: the expected value of keff.

void MCNPSource::SetKSRC

(

)

[inline]

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

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

Allow to modify a KSRC point source position.

void MCNPSource::SetNormal

(

double

nrm

)

[inline]

Set the normal direction of source (inward or outward)

void MCNPSource::SetNPS

(

int

NPS = 10000

)

[inline]

set the number of source particles (default=10 000).

void MCNPSource::SetParticleDistribution

(

string

ParticleDistribution

)

[inline]

set the Particle Distibution if more than one particle type

void MCNPSource::SetParticleType

(

int

particle

)

[inline]

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

void MCNPSource::SetPosition

(

double *

pos = 0

)

set the position of a point source (SDEF) (in m)

void MCNPSource::SetPosition	(	double	x = 0,
		double	y = 0,
		double	z = 0
	)

set the position of a point source (SDEF) (in m)

void MCNPSource::SetRadius

(

string

rad

)

[inline]

set the Radius bias

void MCNPSource::SetSurface

(

int

num

)

[inline]

set the Surface number for a surface source.

void MCNPSource::SetSurface

(

Shape_ptr

TheShape

)

[inline]

set the Surface number for a surface source.

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

Set the reference vector for DIR.

void MCNPSource::SetVEC

(

string

vec

)

void MCNPSource::SetWeight

(

double

wgt

)

[inline]

set the Source particle weight

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

int MCNPSource::fActiveCycle [private]

number of active cycles in KCODE

vector<string> MCNPSource::fAXS [private]

Reference vector for ext and rad.

vector<string> MCNPSource::fBias [private]

vector of bias

string MCNPSource::fDirection [private]

direction bias

string MCNPSource::fDistribution [private]

source distribution (use with bias)

string MCNPSource::fEnergy [private]

Energy of the Source (either a number or a bias)

string MCNPSource::fEXT [private]

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

bool MCNPSource::fExtern [private]

whether the source is extern or defined in MCNP file

int MCNPSource::fInactiveCycle [private]

number of inactive cycles in KCODE

bool MCNPSource::fKcode [private]

whether or not a KCODE is wanted

double MCNPSource::fKeff [private]

expected Keff in KCODE

bool MCNPSource::fKSRC [private]

whether or not a KSRC source is wanted

vector<double*> MCNPSource::fKSRCposition [private]

KSRC position vector.

double MCNPSource::fNormal [private]

Normal direction (inward or outward) for particle source.

int MCNPSource::fNPS [private]

number of source particles

string MCNPSource::fParticleDistribution [private]

if not only one particle

int MCNPSource::fParticleType [private]

particle type for the source (1=neutron)

double* MCNPSource::fPosition [private]

Position of the point Source (if it is the case)

string MCNPSource::fRadius [private]

direction bias

vector<Tube*> MCNPSource::fSourceTube [private]

vector of Tube for <> sources

int MCNPSource::fSurface [private]

Surface number for surface source (if it is the case)

Shape_ptr MCNPSource::fSurfaceShape [private]

Surface Shape for surface source (if it is the case)

vector<string> MCNPSource::fTubeParticleEnergy [private]

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

vector<Spectrum*> MCNPSource::fTubeParticleSpectrum [private]

vector of energy spectrum if the source uses Spectrum

vector<string> MCNPSource::fVEC [private]

Reference vector for DIR.

double MCNPSource::fWeight [private]

weight of the source

---

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

• /0gpr/meplan/MURE/source/include/MCNPSource.hxx
• /0gpr/meplan/MURE/source/src/MCNPSource.cxx