A real Nucleus with a Temperature. More...
#include <Nucleus.hxx>
Public Member Functions | |
Nucleus (int Z, int A, int I=0, bool Moderator=0, bool Evolution=false) | |
Normal Constructor for Nucleus. More... | |
Nucleus (int Z, int A, int I, double T, bool Moderator=0, bool Evolution=false) | |
Constructor for Nucleus at T. More... | |
Nucleus (ZAI *zai, double T, bool Moderator=0, bool Evolution=false) | |
Constructor for Nucleus at T. More... | |
Nucleus (const Nucleus &n, bool clone=false) | |
Copy constructor. More... | |
~Nucleus () | |
Normal destructor. More... | |
ZAI main attributes | |
int | Z () |
returns the number of protons More... | |
int | A () |
returns the number of nucleons More... | |
int | I () |
returns the Isomeric state (Ground State, ith excited) More... | |
ZAI * | GetZAI () |
returns the ZAI* of the Nucleus More... | |
void | SetZAI (ZAI *zai) |
set the ZAI* of the Nucleus More... | |
double | GetMass () |
Returns the mass of this nucleus. More... | |
void | SetMass (double m) |
Set the mass of this nucleus. More... | |
double | GetTemperature () |
returns the nucleus temperature (K) More... | |
void | SetTemperature (double T) |
set the nucleus temperature (K) More... | |
bool | GetModerator () |
returns wether or not the nucleus is a Moderator More... | |
string | GetModeratorLine () |
returns wether or not the nucleus is a Moderator More... | |
void | SetModeratorName (string name) |
Set the name of the moderator MT card. More... | |
void | SetModeratorLine (string line) |
Set the XSDIR line of the moderator MT card. More... | |
void | SetModeratorCategory (string ModeratorCatgory) |
Set the moderator category. More... | |
Find Nucleus in data base methods | |
string | FindMCNPCode () |
Find the closest MCNP code of the nucleus. More... | |
void | FindMCNPCode2 () |
Find the secondary MCNP code of the nucleus. More... | |
void | SetXSExtension (string code) |
allows user to override the XS id code for MCNP More... | |
void | SetXSDIRLine (string Line) |
If SetXSExtension has been used, this method gives the right XSDIR line. More... | |
string | GetIdCode () |
Returns the Extension of this nucleus. More... | |
string | GetIdCode2 () |
Returns the alternative Extension of this nucleus. More... | |
void | SetIdCode (string code="") |
set the Extension of this nucleus. More... | |
string | GetBestLine () |
Gives the best BaseSummary line for this nucleus. More... | |
string | GetBestLine2 () |
Gives the second best BaseSummary line for this nucleus. More... | |
void | SetBestLine (string BestLine) |
Changes the best BaseSummary line for this nucleus. More... | |
void | SetGlobalNucleiIndex (int Index) |
set index of this nucleus in the Global Nuclei vector of MURE. More... | |
string | FindMCNPModeratorName () |
find MCNP moderator name (e.g. grph.01t) More... | |
double | FindCode (double Temperature, string Type, bool AllWarning=false) |
Find either Nucleus MCNP code, or Moderator MCNP code. More... | |
void | SetXSCode (vector< int > XSC) |
Set the array of reaction codes in tally multiplier bins. More... | |
vector< int > | GetXSCode () |
return the array of reaction codes in tally multiplier bins More... | |
bool | IsUserCode () |
Points out if the extension has been given by the user. More... | |
Cross-section & reaction rate methods | |
ValErr_t | GetMCNPSigmaPhiFM (int BinNum, int FMBinNum) |
returns the disparition rate from the nucleus for a given FM bin number. More... | |
double | GetSigmaPhi (int BinNum, int ReactionCode) |
returns the disparition rate from the nucleus to its daughter. More... | |
double | GetSigmaPhi2 (int BinNum, int ReactionCode) |
returns the disparition rate from the nucleus to its daughter. More... | |
ValErr_t | GetMCNPSigmaPhi (int BinNum, int ReactionCode) |
returns the disparition rate from the nucleus to its daughter. More... | |
ValErr_t | GetMCNPSigmaPhi2 (int BinNum, int ReactionCode) |
returns the disparition rate from the nucleus to its daughter. More... | |
double | GetSigmaPhi (Cell *cell, ZAI *daughter) |
returns the disparition rate from the nucleus to its daughter. More... | |
ValErr_t | GetMCNPSigmaPhi (Cell *cell, ZAI *daughter) |
returns the disparition rate from the nucleus to its daughter. More... | |
double | GetSigmaPhi (Cell *cell, int ReactionCode) |
returns the disparition rate of the nucleus according to the reaction code. More... | |
double | GetSigmaPhi2 (Cell *cell, int ReactionCode) |
returns the disparition rate of the nucleus according to the reaction code. More... | |
ValErr_t | GetMCNPSigmaPhi (Cell *cell, int ReactionCode) |
returns the disparition rate of the nucleus according to the reaction code. More... | |
ValErr_t | GetMCNPSigmaPhi2 (Cell *cell, int ReactionCode) |
returns the disparition rate of the nucleus according to the reaction code. More... | |
void | SetMCNPSigmaPhi (int BinNum, int FMBinNum, ValErr_t r) |
Set the disparition rate from the nucleus to its daughter. More... | |
void | SetMCNPSigmaPhi2 (int BinNum, int FMBinNum, ValErr_t r) |
Set the disparition rate from the nucleus to its daughter. More... | |
void | SetMCNPSigma (int BinNum, int FMBinNum, ValErr_t xs) |
Set the cross section from the nucleus to its daughter. More... | |
void | SetMCNPSigma2 (int BinNum, int FMBinNum, ValErr_t xs) |
Set the cross section from the nucleus to its daughter. More... | |
double | GetSigmaFM (int BinNum, int FMBinNum) |
returns the cross-section of the nucleus according to FM bin number. More... | |
ValErr_t | GetMCNPSigmaFM (int BinNum, int FMBinNum) |
returns the cross-section of the nucleus according to FM bin number. More... | |
ValErr_t | GetMCNPSigma (int BinNum, int ReactionCode) |
returns the cross-section of the nucleus according to the reaction code. More... | |
ValErr_t | GetMCNPSigma2 (int BinNum, int ReactionCode) |
returns the cross-section of the nucleus according to the reaction code. More... | |
ValErr_t | GetMCNPSigma (Cell *cell, ZAI *daughter) |
returns the cross-section of the nucleus to its daughter. More... | |
ValErr_t | GetMCNPSigma (Cell *cell, int ReactionCode) |
returns the cross-section of the nucleus according to the reaction code. More... | |
ValErr_t | GetMCNPSigma2 (Cell *cell, int ReactionCode) |
returns the cross-section of the nucleus according to the reaction code. More... | |
void | SetTotalSigma (double xs) |
Set total cross section. More... | |
double | GetTotalSigma () |
returns total cross section More... | |
double | GetTotalSigmaPhi (Cell *cell) |
returns total sigma*phi of cell More... | |
void | SetTotalSigmaPhi (int BinNum, double xs) |
set the total reaction rate More... | |
void | SetFMTotalBinNum (int FMbin) |
set total sigma*phi bin in a tally More... | |
int | GetFMTotalBinNum () |
returns total sigma*phi bin in a tally More... | |
void | SetTallyNumber (int num) |
Set Tally Number for reaction rates. More... | |
int | GetTallyNumber () |
returns Tally Number for reaction rates More... | |
vector< int > | GetFMBinNumber () |
returns FM Tally bin Number VECTOR for reaction rates More... | |
vector< int > | GetBinNumber () |
returns Tally bin Number VECTOR (Cells or Surfaces) More... | |
vector< int > | GetCellNumber () |
vector< int > | SetFMBinNumber (int &FMBinNum) |
Set FM Tally bin Number for reaction rates. More... | |
void | SetBinNumber (int BinNum) |
set the tally bin number (corresponding to cells) More... | |
void | SetCellNumber (int CellNum) |
set the tally bin number (corresponding to cells) More... | |
int | FindFMBin (int ReactionCode) |
Find the FM bin number of the reaction code. More... | |
void | FindSlope (int BinNum, int FMBinNum) |
Find the reaction rate slope for a bin. More... | |
void | FindSmooth (int BinNum, int FMBinNum) |
Find the smooth reaction rate for a bin. More... | |
Miscellaneous methods | |
string | Print () |
Print MCNP code and Proportion of the nucleus. More... | |
string | PrintPseudoNucleus (double proportion) |
Print the nucleus as a pseudo material nucleus (e.g 1001.60c 0.5 1001.70c 0.5) More... | |
void | SetEvolution (bool Evolution) |
Precises the Evolution state (Evolutive or not) More... | |
bool | IsEvolutive () |
Returns the Evolution state (Evolutive or not) More... | |
int | GetGlobalNucleiIndex () |
get index of this nucleus in the Global Nuclei vector of MURE. More... | |
void | ResetFirstReaction () |
Set all fFirstReaction to true. More... | |
bool | IsFirstReaction (int ReactionCode) |
returns the fFirstReaction[ReactionCode] More... | |
void | SetFirstReaction (int ReactionCode) |
Set the fFirstReaction[ReactionCode] to false. More... | |
void | Duplicate (bool flag) |
Say that a nucleus is duplicate in a material. More... | |
bool | IsDuplicate () |
whether or not a nucleus is duplicate More... | |
void | SetAlreadyWarn (bool flag=true) |
true when a 1st warning occur in Material::print() More... | |
bool | IsAlreadyWarn () |
return true when a 1st warning occur in Material::print() More... | |
bool | IsTemperatureEvolution () |
say if the nucleus temperature is going to evolved. More... | |
bool | IsPseudoNucleus () |
void | SetPseudoNucleus (bool flag=true) |
void | SetTemperatureEvolution (bool flag=true) |
Set that this nuc is a pseudo nuc. More... | |
void | ClearBinVector () |
erase the vector containg Tally bins More... | |
void | ClearFMBinVector () |
erase the vector containg Tally multiplicator bins More... | |
void | SetNuSigmaFisPhi (int BinNum, double Value) |
Set Nu tot sigma phi (E) More... | |
vector< double > | GetNuSigmaFisPhi () |
Get Nu tot sigma phi vector. More... | |
double | GetNuSigmaFisPhi (int BinNum) |
Get Nu tot sigma phi function of energy. More... | |
double | GetNuSigmaFisPhi (Cell *cell) |
Get Nu tot sigma phi function of a cell. More... | |
Public Member Functions inherited from TReference | |
TReference () | |
Default constructor. Number of references is set to 0. More... | |
virtual | ~TReference () |
Destructor. More... | |
void | AddReference (unsigned n=1) |
Add n references to an object. More... | |
unsigned | DelReference (unsigned n=1) |
Remove n references to an object. More... | |
unsigned | Reference () |
returns the Number of references to an object More... | |
Private Member Functions | |
void | InitSigmaPhi () |
init reaction rate array More... | |
int | FindReactionCode (ZAI *daughter) |
Find the Reaction code that leeds to daughter. More... | |
int | FindCellBin (Cell *cell) |
Find the tally bin number of cell. More... | |
int | NumberOfReaction () |
returns the number of different reactions More... | |
bool | IsModeratorCategoryOk (string Code) |
returns true is Code and fModeratorCategory are compatible More... | |
Private Attributes | |
ZAI * | fZAI |
Pointer on the ZAI. More... | |
bool | fModerator |
whether or not apply a S(alpha,Beta) thermal treatment More... | |
bool | fEvolution |
whether or not it is an evolutive nucleus More... | |
bool | fUserCode |
whether or not the user has given the extension, by a SetXSExtension() More... | |
bool | fPseudoNucleus |
whether or not nucleus is a pseudo nucleus More... | |
string | fModeratorName |
MCNP moderator name (e.g. grph.01t) More... | |
string | fModeratorLine |
XSDIR moderator line. More... | |
string | fModeratorCategory |
Moderator category for automatic moderator name. More... | |
string | fIdCode |
MCNP id code for the closest cross-section (.60c) More... | |
string | fIdCode2 |
MCNP id code for the second closest cross-section (.60c) More... | |
double | fTemperature |
The temperature of the nucleus. More... | |
double | fBaseTemperature1 |
Closest Base temperature to fTemperature. More... | |
double | fBaseTemperature2 |
Second closest Base temperature to fTemperature. More... | |
int | fGlobalNucleiIndex |
Index of this nucleus in the Global nuclei vector. More... | |
string | fBestLine |
Best line of the BaseSummary.dat for this Nucleus. More... | |
string | fBestLine2 |
Second best line of the BaseSummary.dat for this Nucleus. More... | |
int | fTallyNum |
Tally Number for reaction rates. More... | |
vector< int > | fFMBinNum |
FM Tally bin Number for reaction rate. More... | |
vector< int > | fBinNum |
Tally bin Number (for reaction rate) More... | |
vector< int > | fCellNum |
Cell/Surface Number (fBinNum[i]<=>fCellNum[i]) More... | |
vector< vector< vector < ValErr_t > > > | fSigmaPhi |
Reaction rates. More... | |
vector< vector< vector < ValErr_t > > > | fSigmaPhi2 |
Reaction rates. More... | |
vector< vector< ValErr_t > > | fMCNPSigmaPhi |
MCNP Reaction rates. More... | |
vector< vector< ValErr_t > > | fMCNPSigmaPhi2 |
MCNP Reaction rates. More... | |
vector< vector< ValErr_t > > | fMCNPSigmaPhi3 |
MCNP Reaction rates for PCE fit in corrector step. More... | |
vector< vector< ValErr_t > > | fMCNPSigma |
Cross-sections. More... | |
vector< vector< ValErr_t > > | fMCNPSigma2 |
Cross-sections. More... | |
vector< double > | fTotalSigmaPhi |
Total sigma phi in each Tally bin. More... | |
int | fFMTotalBinNum |
FM Tally bin Number for total reaction rate. More... | |
double | fTotalSigma |
Total cross section. More... | |
int | fNReaction |
Number of different reactions. More... | |
map< int, bool > | fFirstReaction |
a map of Reaction code to bool More... | |
vector< double > | fMCNPTime |
vector of last MCNP run time More... | |
vector< vector< double > > | fFitSlope |
slope to find the sigma*phi extrapolation More... | |
vector< vector< double > > | fIntersept |
intersept to find the sigma*phi extrapolation or the Smooth value if used More... | |
vector< vector< double > > | fFitSlope2 |
slope to find the sigma*phi extrapolation More... | |
vector< vector< double > > | fIntersept2 |
intersept to find the sigma*phi extrapolation More... | |
bool | fDuplicate |
True for duplicate nucleus in composition. More... | |
bool | fAlreadyWarn |
true when a 1st warning occur in Material::print() More... | |
bool | fTemperatureEvolution |
whether or not temperature will evolve More... | |
bool ** | fASK |
temporary flag.... More... | |
vector< int > | fXSCode |
array of reaction codes in tally multiplier bins More... | |
vector< double > | fNuSigmaFisPhi |
Nu tot sigma micro phi. More... | |
A real Nucleus with a Temperature.
A Nucleus is defined by its ZAI and its temperature. It could evolve and thus has a vector of Sigma*Phi calculated by MCNP in the cell where the nucleus has been put.
A Nucleus could be a "Moderator" to use S(alpha,Beta) treatment in MCNP for En<4 eV.
A Nucleus could be in one or more Cell ; if that cells evolved, then a "group" evolution is carried out.
Automatic MCNP name is search in the BaseSummary.dat file. If a user do not have such file and don't want to build it (see XSDIR class) he can use the Nucleus::SetXSExtension(), Material::SetDefaultXSExtension() and Material::SetModeratorName().
NOTE: Natural isotopes have A=0 (then they can't evolve!!!).
Nucleus::Nucleus | ( | int | Z, |
int | A, | ||
int | I = 0 , |
||
bool | Moderator = 0 , |
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bool | Evolution = false |
||
) |
Normal Constructor for Nucleus.
Default: it is ground state (Z,A) and not a moderator.
Z | : number of protons of nucleus |
A | : number of nucleons (A=0 means natural isotopes) |
I | : Isomeric state (0=ground state, 1 =first excited, ...) |
Moderator | : wether or not apply a S(alpha,Beta) thermal treatment |
Evolution | : wether or not the nucleus evolved |
Nucleus::Nucleus | ( | int | Z, |
int | A, | ||
int | I, | ||
double | T, | ||
bool | Moderator = 0 , |
||
bool | Evolution = false |
||
) |
Constructor for Nucleus at T.
Use by Material.
Z | : number of protons of nucleus |
A | : number of nucleons (A=0 means natural isotopes) |
I | : Isomeric state (0=ground state, 1 =first excited, ...) |
T | : Nucleus Temperature (taken from the material) |
Moderator | : wether or not apply a S(alpha,Beta) thermal treatment |
Evolution | : wether or not the nucleus evolved |
Nucleus::Nucleus | ( | ZAI * | zai, |
double | T, | ||
bool | Moderator = 0 , |
||
bool | Evolution = false |
||
) |
Nucleus::Nucleus | ( | const Nucleus & | n, |
bool | clone = false |
||
) |
Copy constructor.
Nucleus::~Nucleus | ( | ) |
Normal destructor.
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returns the number of nucleons
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erase the vector containg Tally bins
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erase the vector containg Tally multiplicator bins
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Say that a nucleus is duplicate in a material.
This appends when 2 nucleus of a given material have the same MCNP code. This is the case when 1 isomeric state of a nucleus is not in the Database but a other exist: then the missing state is replaced by a existing one (the closest). This is to avoid MCNP warning.
flag | : true for duplicate nucleus |
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private |
Find the tally bin number of cell.
double Nucleus::FindCode | ( | double | Temperature, |
string | Type, | ||
bool | AllWarning = false |
||
) |
Find either Nucleus MCNP code, or Moderator MCNP code.
Find the code for desired Temperature and returns the base Temperature
Temperature | : the wanted temperature |
Type | : either "nucleus", "moderator" or "mass" depending on what is searched |
AllWarning | : print all warnings if true, else only some of them |
int Nucleus::FindFMBin | ( | int | ReactionCode | ) |
Find the FM bin number of the reaction code.
string Nucleus::FindMCNPCode | ( | ) |
Find the closest MCNP code of the nucleus.
This is the code for xsdir correponding to the closest temperature
void Nucleus::FindMCNPCode2 | ( | ) |
Find the secondary MCNP code of the nucleus.
The code corresponds to the next closest base temperature. This is used for pseudo-Material.
string Nucleus::FindMCNPModeratorName | ( | ) |
find MCNP moderator name (e.g. grph.01t)
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private |
Find the Reaction code that leeds to daughter.
void Nucleus::FindSlope | ( | int | BinNum, |
int | FMBinNum | ||
) |
Find the reaction rate slope for a bin.
void Nucleus::FindSmooth | ( | int | BinNum, |
int | FMBinNum | ||
) |
Find the smooth reaction rate for a bin.
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Gives the best BaseSummary line for this nucleus.
string Nucleus::GetBestLine2 | ( | ) |
Gives the second best BaseSummary line for this nucleus.
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returns Tally bin Number VECTOR (Cells or Surfaces)
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returns Cell Number VECTOR (Cells or Surfaces)
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returns FM Tally bin Number VECTOR for reaction rates
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returns total sigma*phi bin in a tally
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get index of this nucleus in the Global Nuclei vector of MURE.
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Returns the Extension of this nucleus.
string Nucleus::GetIdCode2 | ( | ) |
Returns the alternative Extension of this nucleus.
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Returns the mass of this nucleus.
ValErr_t Nucleus::GetMCNPSigma | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the cross-section of the nucleus according to the reaction code.
BinNum | : the cell/surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
returns the cross-section of the nucleus to its daughter.
cell | : the Cell where reaction rates are calculated |
daughter | : the zai identifying the daughter |
ValErr_t Nucleus::GetMCNPSigma | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the cross-section of the nucleus according to the reaction code.
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigma2 | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the cross-section of the nucleus according to the reaction code.
Same as previous except it is for Partial MCNP run
BinNum | : the cell/surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigma2 | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the cross-section of the nucleus according to the reaction code.
Same as previous except it is for Partial MCNP run
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigmaFM | ( | int | BinNum, |
int | FMBinNum | ||
) |
returns the cross-section of the nucleus according to FM bin number.
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number |
ValErr_t Nucleus::GetMCNPSigmaPhi | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value
BinNum | : the cell/surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value
cell | : the Cell where reaction rates are calculated |
daughter | : the zai identifying the daughter |
ValErr_t Nucleus::GetMCNPSigmaPhi | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the disparition rate of the nucleus according to the reaction code.
This value is not normalized : it is the MCNP value
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigmaPhi2 | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value Same as previous except it is for Partial MCNP run
BinNum | : the cell/surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigmaPhi2 | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the disparition rate of the nucleus according to the reaction code.
This value is not normalized : it is the MCNP value Same as previous except it is for Partial MCNP run
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
ValErr_t Nucleus::GetMCNPSigmaPhiFM | ( | int | BinNum, |
int | FMBinNum | ||
) |
returns the disparition rate from the nucleus for a given FM bin number.
This value is not normalized : it is the MCNP value
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number |
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returns wether or not the nucleus is a Moderator
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returns wether or not the nucleus is a Moderator
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Get Nu tot sigma phi vector.
double Nucleus::GetNuSigmaFisPhi | ( | int | BinNum | ) |
Get Nu tot sigma phi function of energy.
double Nucleus::GetNuSigmaFisPhi | ( | Cell * | cell | ) |
Get Nu tot sigma phi function of a cell.
double Nucleus::GetSigmaFM | ( | int | BinNum, |
int | FMBinNum | ||
) |
returns the cross-section of the nucleus according to FM bin number.
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number |
double Nucleus::GetSigmaPhi | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value
BinNum | : the cell/Surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value
cell | : the Cell where reaction rates are calculated |
daughter | : the zai identifying the daughter |
double Nucleus::GetSigmaPhi | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the disparition rate of the nucleus according to the reaction code.
This value is not normalized : it is the MCNP value
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
double Nucleus::GetSigmaPhi2 | ( | int | BinNum, |
int | ReactionCode | ||
) |
returns the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value Same as previous except it is for Partial MCNP run
BinNum | : the cell/surface bin number where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
double Nucleus::GetSigmaPhi2 | ( | Cell * | cell, |
int | ReactionCode | ||
) |
returns the disparition rate of the nucleus according to the reaction code.
This value is not normalized : it is the MCNP value Same as previous except it is for Partial MCNP run
cell | : the Cell where reaction rates are calculated |
ReactionCode | : the reaction code (ENDF Type) |
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returns Tally Number for reaction rates
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returns the nucleus temperature (K)
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returns total cross section
double Nucleus::GetTotalSigmaPhi | ( | Cell * | cell | ) |
returns total sigma*phi of cell
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return the array of reaction codes in tally multiplier bins
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returns the Isomeric state (Ground State, ith excited)
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init reaction rate array
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return true when a 1st warning occur in Material::print()
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whether or not a nucleus is duplicate
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Returns the Evolution state (Evolutive or not)
bool Nucleus::IsFirstReaction | ( | int | ReactionCode | ) |
returns the fFirstReaction[ReactionCode]
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returns true is Code and fModeratorCategory are compatible
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say if the nucleus temperature is going to evolved.
When this is true, this means that the nucleus will be duplicated in the MURE::fGlobalNucleiVector. The default is false.
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Points out if the extension has been given by the user.
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returns the number of different reactions
string Nucleus::Print | ( | ) |
Print MCNP code and Proportion of the nucleus.
string Nucleus::PrintPseudoNucleus | ( | double | proportion | ) |
Print the nucleus as a pseudo material nucleus (e.g 1001.60c 0.5 1001.70c 0.5)
void Nucleus::ResetFirstReaction | ( | ) |
Set all fFirstReaction to true.
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true when a 1st warning occur in Material::print()
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Changes the best BaseSummary line for this nucleus.
void Nucleus::SetBinNumber | ( | int | BinNum | ) |
set the tally bin number (corresponding to cells)
void Nucleus::SetCellNumber | ( | int | CellNum | ) |
set the tally bin number (corresponding to cells)
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inline |
Precises the Evolution state (Evolutive or not)
void Nucleus::SetFirstReaction | ( | int | ReactionCode | ) |
Set the fFirstReaction[ReactionCode] to false.
vector< int > Nucleus::SetFMBinNumber | ( | int & | FMBinNum | ) |
Set FM Tally bin Number for reaction rates.
Fills FM Tally bin Number vector starting at bin "num" to num+nb of reactions+1. Output: num is set to num+(nb of reactions)+1 and a vector of XS codes (ENDF type) is given
FMBinNum | : input: starting bin for the first reaction, ouput: FMBinNum+last bin for the last reaction+1 |
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set total sigma*phi bin in a tally
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set index of this nucleus in the Global Nuclei vector of MURE.
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set the Extension of this nucleus.
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Set the mass of this nucleus.
void Nucleus::SetMCNPSigma | ( | int | BinNum, |
int | FMBinNum, | ||
ValErr_t | xs | ||
) |
Set the cross section from the nucleus to its daughter.
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number for a given reaction |
xs | : the cross-section |
void Nucleus::SetMCNPSigma2 | ( | int | BinNum, |
int | FMBinNum, | ||
ValErr_t | xs | ||
) |
Set the cross section from the nucleus to its daughter.
Same as previous except it is for Partial MCNP run
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number for a given reaction |
xs | : the cross-section |
void Nucleus::SetMCNPSigmaPhi | ( | int | BinNum, |
int | FMBinNum, | ||
ValErr_t | r | ||
) |
Set the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number for a given reaction |
r | : the reaction rate |
void Nucleus::SetMCNPSigmaPhi2 | ( | int | BinNum, |
int | FMBinNum, | ||
ValErr_t | r | ||
) |
Set the disparition rate from the nucleus to its daughter.
This value is not normalized : it is the MCNP value Same as previous except it is for Partial MCNP run
BinNum | : the cell/surface bin number where reaction rates are calculated |
FMBinNum | : the FM bin number for a given reaction |
r | : the reaction rate |
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inline |
Set the moderator category.
This category is used in automatic moderator name assignement. If moderator name is given with Material::SetModeratorName(), the content of ModeratorCatgory is unused. The category is one of: - H2O is for H in light water, - H/Zr for H in ZrH, - poly for H in polyethylene, - D2O for D in heavy water, - BeO for Be in Be oxyde, - Be for Be in Be metal - Gr for graphite, - Zr/H for Zr in ZrH,
ModeratorCatgory | : The catergory of the moderator ("H2O", "D2O", ...) |
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Set the XSDIR line of the moderator MT card.
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Set the name of the moderator MT card.
void Nucleus::SetNuSigmaFisPhi | ( | int | BinNum, |
double | Value | ||
) |
Set Nu tot sigma phi (E)
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inline |
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Set Tally Number for reaction rates.
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set the nucleus temperature (K)
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Set that this nuc is a pseudo nuc.
set the Temperature evolution flag
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Set total cross section.
void Nucleus::SetTotalSigmaPhi | ( | int | BinNum, |
double | xs | ||
) |
set the total reaction rate
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Set the array of reaction codes in tally multiplier bins.
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inline |
If SetXSExtension has been used, this method gives the right XSDIR line.
void Nucleus::SetXSExtension | ( | string | code | ) |
allows user to override the XS id code for MCNP
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inline |
returns the number of protons
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private |
true when a 1st warning occur in Material::print()
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private |
temporary flag....
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private |
Closest Base temperature to fTemperature.
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private |
Second closest Base temperature to fTemperature.
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private |
Best line of the BaseSummary.dat for this Nucleus.
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private |
Second best line of the BaseSummary.dat for this Nucleus.
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private |
Tally bin Number (for reaction rate)
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private |
Cell/Surface Number (fBinNum[i]<=>fCellNum[i])
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private |
True for duplicate nucleus in composition.
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private |
whether or not it is an evolutive nucleus
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private |
a map of Reaction code to bool
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private |
slope to find the sigma*phi extrapolation
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private |
slope to find the sigma*phi extrapolation
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private |
FM Tally bin Number for reaction rate.
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private |
FM Tally bin Number for total reaction rate.
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private |
Index of this nucleus in the Global nuclei vector.
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private |
MCNP id code for the closest cross-section (.60c)
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private |
MCNP id code for the second closest cross-section (.60c)
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private |
intersept to find the sigma*phi extrapolation or the Smooth value if used
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private |
intersept to find the sigma*phi extrapolation
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private |
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private |
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private |
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private |
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private |
MCNP Reaction rates for PCE fit in corrector step.
the first dimension of this vector is associated with the Cell/Surface Tally bin number (one to one) the second dimension is associated with the FM Tally bin number, (one to one) It stores the Reaction rates of the corrector step in PCE to make a fit from fMCNPSigmaPhi (predictor) to fMCNPSigmaPhi3 during RK integration
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private |
vector of last MCNP run time
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private |
whether or not apply a S(alpha,Beta) thermal treatment
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private |
Moderator category for automatic moderator name.
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private |
XSDIR moderator line.
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private |
MCNP moderator name (e.g. grph.01t)
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private |
Number of different reactions.
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private |
Nu tot sigma micro phi.
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private |
whether or not nucleus is a pseudo nucleus
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private |
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private |
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private |
Tally Number for reaction rates.
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private |
The temperature of the nucleus.
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private |
whether or not temperature will evolve
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private |
Total cross section.
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private |
Total sigma phi in each Tally bin.
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private |
whether or not the user has given the extension, by a SetXSExtension()
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private |
array of reaction codes in tally multiplier bins