From 7dfcc480ba1e19bd3232349fc733caef94034292 Mon Sep 17 00:00:00 2001 From: stainer_t Date: Mon, 8 Sep 2025 13:48:49 +0200 Subject: Initial commit from Polytechnique Montreal --- doc/IGE344/SectFLPOW.tex | 176 +++++++++++++++++++++++++++++++++++++++++++++++ 1 file changed, 176 insertions(+) create mode 100644 doc/IGE344/SectFLPOW.tex (limited to 'doc/IGE344/SectFLPOW.tex') diff --git a/doc/IGE344/SectFLPOW.tex b/doc/IGE344/SectFLPOW.tex new file mode 100644 index 0000000..ba69b72 --- /dev/null +++ b/doc/IGE344/SectFLPOW.tex @@ -0,0 +1,176 @@ +\subsection{The \moc{FLPOW:} module}\label{sect:flpow} + +\vskip 0.2cm +The \moc{FLPOW:} module is used to compute and print the flux and power +distributions over the reactor core. It also computes and prints some additional +information, for example: the fluxes ratios with respect to the thermal energy-group +fluxes; the mean power density; the power- and flux-form factors; etc. The computed +fluxes and powers are printed either on files or on the screen. Note that the calculation +using the \moc{FLPOW:} module can be performed once the numerical solution has +been previously established using the \moc{FLUD:} or \moc{KINSOL:} module.\\ + +According to the user-selected module specification, the average fluxes and +powers can be computed per each fuel region over the fuel lattice \dusa{and/or} +per each material region over the whole reactor geometry. In either case, all fluxes +are normalized to the given total reactor power corresponding to the reactor nominal +conditions at core equilibrium. If the reactor is perturbed from its initial state, then a +new total reactor power can be recomputed and, accordingly, the flux and power +distributions will be updated using the previously computed normalization factor.\\ + +The \moc{FLPOW:} module will create a new \moc{POWER} object that will store +the information related to the reactor fluxes and powers (see \Sect{power}). In addition, +the \moc{POWER} object will store several parameters that can be used as power +and criticity constraints for the optimization and fuel management purposes, namely: +the maximum channel and bundle powers; the channel and bundle power-form factors; +the effective multiplication factor (recovered from the \dds{flux} or \dds{kinet} data structure).\\ + +\noindent +The \moc{FLPOW:} module specifications are: + +\begin{DataStructure}{Structure \moc{FLPOW:}} +$\{$ \\ +~~~\dusa{POWER} $[$ \dusa{NRMFLUX} $]~[$ \dusa{FMAP} $]$ \\ +~~~~~~~~\moc{:=} \moc{FLPOW:} $[$ \dusa{POWOLD} $]$ \dusa{FMAP} +$\{$ \dusa{FLUX} $|$ \dusa{KINET} $\}$ \dusa{TRACK} \dusa{MATEX} $[$ \dusa{MACRO} $]$ \\ +~~~~~~~~\moc{::} \dstr{descflpow} \\ +$|$ \\ +~~~\dusa{POWER} \moc{:=} \moc{FLPOW:} $[$ \dusa{POWOLD} $]$ +$\{$ \dusa{FLUX} $|$ \dusa{KINET} $\}$ \dusa{TRACK} \dusa{MACRO} \\ +~~~~~~~~\moc{::} \dstr{descflpow} \\ + $\}$ + \end{DataStructure} + +\noindent where + +\begin{ListeDeDescription}{mmmmmmmm} + +\item[\dusa{POWER}] \texttt{character*12} name of the \dds{power} object +that will be created by the module. It will contain the information related to the +reactor fluxes and powers. + +\item[\dusa{NRMFLUX}] \texttt{character*12} name of the \dds{flux} object, +in creation mode. According to the chosen option, this object contains either +the fluxes normalized to the given total reactor power or the fluxes per bundle. +Is it useful if you want to compute the detectors readings with the \moc{DETECT:} module. + +\item[\dusa{POWOLD}] \texttt{character*12} name of the read-only \dds{power} +object. It must contain the previously computed flux normalization factor, which +corresponds to the reactor nominal or equilibrium conditions. + +\item[\dusa{FMAP}] \texttt{character*12} name of the \dds{fmap} object +containing the fuel lattice specification. When \dusa{FMAP} is specified on the RHS, +the fluxes and powers calculations are performed over the fuel lattice as well +as over the whole reactor geometry. If \dusa{FMAP} is specified on the LHS, its +records \moc{'BUND-PW'} and \moc{'FLUX-AV'} will be set according to the +information present in \dusa{POWER}. + +\item[\dusa{FLUX}] \texttt{character*12} name of the \dds{flux} object, +previously created by the \moc{FLUD:} module. The numerical flux solution +contained in \dusa{FLUX} is recovered and all flux are normalized to the +given total reactor power. + +\item[\dusa{KINET}] \texttt{character*12} name of the \dds{kinet} object, +previously created by the \moc{KINSOL:} module. The numerical flux solution +contained in \dusa{KINET} is recovered. + +\item[\dusa{TRACK}] \texttt{character*12} name of the \dds{track} object, +created by the \moc{TRIVAT:} module. The information stored in \dusa{TRACK} +is recovered and used for the average flux calculation. + +\item[\dusa{MATEX}] \texttt{character*12} name of the \dds{matex} object, +containing the reactor material index and the h-factors that will be recovered +and used for the power calculation. + +\item[\dusa{MACRO}] \texttt{character*12} name of the \dds{macrolib} object, +containing the h-factors that will be recovered and used for the power calculation. + +\item[\dstr{descflpow}] structure describing the input data to the \moc{FLPOW:} +module . + +\end{ListeDeDescription} + +\vskip 0.2cm + +\subsubsection{Input data to the \moc{FLPOW:} module} + +\noindent +Note that the fuel-lattice power distribution can be printed only on the screen.\\ + +\begin{DataStructure}{Structure \dstr{descflpow}} + +$[$ \moc{EDIT} \dusa{iprint} $]$ \\ +$[~\{$ \moc{PTOT} \dusa{power} $|$ \moc{P-NEW} $\}~]$ \\ +$[$ \moc{FSTH} \dusa{fsth} $]~[$ \moc{INIT} $]$ \\ +$[~\{$ \moc{NORM} $|$ \moc{BUND} $\}~]$ \\ +$[$ \moc{PRINT} $\{$ \moc{MAP} $|$ \moc{DISTR} $[$ \moc{FLUX} $]$ +$[$ \moc{RATIO} $]$ $[$ \moc{POWER} $]$ $|$ \moc{ALL} $\}$ $]$ \\ +; +\end{DataStructure} + +\noindent where +\begin{ListeDeDescription}{mmmmmmmm} + +\item[\moc{EDIT}] keyword used to set \dusa{iprint}. + +\item[\dusa{iprint}] integer index used to control the printing on screen: + = 0 for no print; = 1 for minimum editing (default value); = 2 only channel powers in radial +plane are printed; = 3 only bundle powers per each radial plane are printed; = 10 only bundle powers per each channel are printed. Any combination of the values 2, 3 and 10 is possible, for example 5 = 2+3. Note that any other value of \dusa{iprint} behaves as the first lower possible value, for example 7 gives the same output as 5. Moreover channel and bundle powers can be printed only if the \dusa{FMAP} object was provided in the calling specification. + +\item[\moc{PTOT}] keyword used to specify the input of \dusa{power}. By default, a power is recovered from the \dusa{KINET} object. + +\item[\dusa{power}] real total reactor power, given in MW. This value +must correspond to the reactor nominal conditions. + +\item[\moc{FSTH}] keyword to specify the thermal to fission power ratio. + +\item[\dusa{fsth}] thermal to fission power ratio. By default this value is not used, and the total +power is the one given after the \moc{PTOT} keyword. + +\item[\moc{INIT}] keyword used to save the actual power distribution in the {\tt BUND-PW-INI} +record of the fuel map object \dusa{FMAP}. It is used by the \moc{AFM:} module to apply power +feedback during a fast transient using the initial power distribution instead of the actual power. + +\item[\moc{P-NEW}] keyword used to indicate that a new total reactor power +is to be recomputed, based on the previously calculated flux normalization factor. +The flux and power distributions over the reactor core are updated, accordingly. +Note that this option is valid only if a read-only \dusa{POWOLD} object is provided. + +\item[\moc{PRINT}] keyword used to indicate the printing on files. Note +that all produced files will have the same extension ``\moc{.res}". + +\item[\moc{MAP}] keyword used to specify the printing of the average fluxes +and flux ratios per fuel bundle. The normalized bundle fluxes are computed +and printed for each reactor channel and per each energy group. The flux +ratios are computed with respect to the thermal energy-group fluxes; they +are printed on the same file. + +\item[\moc{DISTR}] keyword used to indicate the printing of data +computed over the whole reactor geometry. + +\item[\moc{FLUX}] keyword used to specify the printing of flux distribution. +The normalized fluxes are printed in separated files, one file per energy +group; the number of produced files will then equal to the total number +of energy groups. The flux values are printed for each mesh-splitted volume, +in X, Y and Z planes; the virtual regions will have the fluxes values set to 0. + +\item[\moc{RATIO}] keyword used to specify the printing of flux-ratio +distribution. The flux ratios are computed with respect to the thermal +energy-group fluxes per each mesh-splitted volume. They are printed +in separated files; the number of produced files will equal to the total +number of energy groups less one. + +\item[\moc{POWER}] keyword used to specify the printing of power +distribution. The power values are printed for each mesh-splitted volume, +in X, Y, and Z planes; the non-fuel regions will have the power values set to 0. + +\item[\moc{ALL}] keyword used to indicate the printing of all available +information, i.e. without particular selection of data. + +\item[\moc{NORM}] keyword to specify that the output flux object will contain a value per mesh-splitted element, normalized +to the given power, as required by the \moc{DETECT:} module. This is the default option. + +\item[\moc{BUND}] keyword to specify that the output flux object will contain a value per bundle, normalized +to the given power. + +\end{ListeDeDescription} +\clearpage -- cgit v1.2.3