Define a Tally Multiplicator entry (FM card in MCNP). More...
#include <Tally.hxx>
Public Member Functions | |
| TallyFM (Material *M, int reaction, double constant=1) | |
| TallyFM (Material *M, Reaction *R, double constant=1) | |
| TallyFM (int MatNumber, int reaction, double constant=1) | |
| TallyFM (int MatNumber, Reaction *R, double constant=1) | |
| Constructor of Multiplicator Bin. | |
| TallyFM (const TallyFM &fm) | |
| Copy constructor. | |
| ~TallyFM () | |
| Destructor. | |
| string | Print () |
| Print a TallyFM. | |
| int | GetMaterial () |
Private Member Functions | |
| void | Init (int MatNumber, Reaction *R, double constant=1) |
| Build a TallyFM. Called by constructors. | |
Private Attributes | |
| double | fConstant |
| multiplicative constant of the FM | |
| int | fMatNumber |
| Material Number of the FM. | |
| Reaction * | fReaction |
| Reaction of the FM. | |
Define a Tally Multiplicator entry (FM card in MCNP).
| TallyFM::TallyFM | ( | Material * | M, |
| int | reaction, | ||
| double | constant = 1 |
||
| ) |
Constructor of Multiplicator Bin. The Tally Multiplicator will be multiply by the parameter "constant". if constant<0 then constant is replaced by |constant|*(atom density of the cell where Tally is made). For example, if constant=-1 in a cell Flux Tally (F4), for a given reaction, the result will be the the macrosopic cross section * Flux, whereas if constant=1 this will be the microscopic cross section *Flux.
| M | : the Material to consider for the reaction |
| reaction | : a simple reaction code (-1=total, -6=fission,...) |
| constant | : the multiplicative constant of the FM (see above). Default=1; |
| TallyFM::TallyFM | ( | Material * | M, |
| Reaction * | R, | ||
| double | constant = 1 |
||
| ) |
Constructor of Multiplicator Bin. The Tally Multiplicator will be multiply by the parameter "constant".
if constant<0 then constant is replaced by |constant|*(atom density of the cell where Tally is made).
For example, if constant=-1 in a cell Flux Tally (F4), for a given reaction, the result will be the the macrosopic cross section * Flux, whereas if constant=1 this will be the microscopic cross section *Flux.
| TallyFM::TallyFM | ( | int | MatNumber, |
| int | reaction, | ||
| double | constant = 1 |
||
| ) |
Constructor of Multiplicator Bin. see description of TallyFM(Material *M,int reaction,double constant=1)
| MatNumber | : the Material Number to consider for the reaction |
| reaction | : a simple reaction code (-1=total, -6=fission,...) |
| constant | : the multiplicative constant of the FM (see above). Default=1; |
| TallyFM::TallyFM | ( | int | MatNumber, |
| Reaction * | R, | ||
| double | constant = 1 |
||
| ) |
| TallyFM::TallyFM | ( | const TallyFM & | fm | ) |
Copy constructor.
Destructor.
| int TallyFM::GetMaterial | ( | ) | [inline] |
| void TallyFM::Init | ( | int | MatNumber, |
| Reaction * | R, | ||
| double | constant = 1 |
||
| ) | [private] |
Build a TallyFM. Called by constructors.
| string TallyFM::Print | ( | ) |
Print a TallyFM.
double TallyFM::fConstant [private] |
multiplicative constant of the FM
int TallyFM::fMatNumber [private] |
Material Number of the FM.
Reaction* TallyFM::fReaction [private] |
Reaction of the FM.