\subsection{Contents of \dir{d2p\_info} data structure}\label{sect:d2pdir}

A \dir{d2p\_info} data structure is used to store cross sections and 
Saphyb information such as keff, kinf, assembly discontinuity factors. This object has a signature {\tt L\_INFO}; it is created using the \moc{D2P:} module.

\subsubsection{The state-vector content}\label{sect:infostate}

\noindent
The dimensioning parameters $\mathcal{S}_i$, which are stored in the state
vector for this data structure, represent:

\begin{itemize}

\item The number of energy groups $N_{\rm gr} = \mathcal{S}_1$

\item The number of pkey for the generation of the PMAXS file $N_{\rm pk} = \mathcal{S}_2$

\item The number of cross sections recovered using the \moc{SCR:} module $N_{\rm xs} = \mathcal{S}_3$

\item The number of points with respect to burnup $N_{\rm bu}$ = $\mathcal{S}_4$

\item The type of branching calculation requested for the generation of PMAXS tree $I_{\rm grid} = \mathcal{S}_5$

\begin{displaymath} I_{\rm grid} = \left\{
\begin{array}{rl}
 0 & \textrm{default meshing} \\
 1 & \textrm{according to the saphyb content} \\
 2 & \textrm{user defined with global otpion} \\
 3 & \textrm{user defined with add otpion} \\
 4 & \textrm{user defined with add new otpion} \\
\end{array} \right.
\end{displaymath}

\item The number of control rod composition $N_{\rm comp}$ = $\mathcal{S}_6$
\item The number of delay neutron groups $N_{\rm del}$ = $\mathcal{S}_7$
\item The number of columns in assembly $N_{\rm cols}$ = $\mathcal{S}_8$
\item The number of rows in assembly $N_{\rm rows}$ = $\mathcal{S}_9$
\item The computed part of asembly assembly $I_{\rm part}$ = $\mathcal{S}_{10}$
\begin{displaymath} I_{\rm part} = \left\{
\begin{array}{rl}
 0 & \textrm{whole} \\
 1 & \textrm{half} \\
 2 & \textrm{quarter} \\
 3 & \textrm{eighth} \\ 
\end{array} \right.
\end{displaymath}

\item The number of sides in assembly. $N_{\rm surf} = \mathcal{S}_{11}$

\item The number of corners in assembly $N_{\rm corn} = \mathcal{S}_{12}$

\item The number of assembly discontinuity factors per energy groups $N_{\rm adf} = \mathcal{S}_{13}$
\end{itemize}
\clearpage
\noindent
The following records and sub-directories will be found on the first level of \dir{d2p\_info}
directory:

\begin{DescriptionEnregistrement}{Records and sub-directories
 in \dir{d2p\_info} data structure}{7.0cm} \label{tabl:tabinfo}

\CharEnr
 {SIGNATURE\blank{3}}{$*12$}
 {Signature of the \dir{d2p\_info} data structure ($\mathsf{SIGNA}=${\tt L\_INFO\blank{6}}).}

  \IntEnr
  {STATE-VECTOR}{$40$}
  { Vector describing the various parameters associated with this data structure}

\IntEnr
  {BARR\_INFO\blank{3}}{$N_{\rm comp}$}
  { Meaning of control rod in the saphyb object. $N_{comp}$ is the number of composition for control rods (including the unrodded case)}
  

  
\OptDirEnr
 {SAPHYB\_INFO\blank{1}}{$iph\geq 1$}
 {Information related to the saphyb content.}  
 
 \OptDirEnr
 {HELIOS\_HEAD\blank{1}}{$iph\geq 1$}
 {Information related to the header of output \moc{.DRA} file}  
 
 \OptDirEnr
 {GENPMAXS\_INP}{$iph\geq 2$}
 {Information related to the GenPMAXS input file.}  
 
 \OptDirEnr
 {BRANCH\_INFO\blank{1}}{$iph\geq 3$}
 {Information related to the current branch calculation.}  
 
 \OptDirlEnr
 {TH\_DATA\blank{5}}{$N_{\rm bu}$}{$iph\geq 2$}
 {Information related to the invariant T/H data block. Each componant of the list is a directory containing TH data for a single burnup point.}  

\end{DescriptionEnregistrement}

%\subsubsection*{The subdirectory \moc{SAPHYB$\_$INFO}}


\begin{DescriptionEnregistrement}{Records and sub-directories
 in \dir{SAPHYB\_INFO} }{7.0cm} \label{tabl:tabsap}

\CharEnr
 {PKEY\_NAME\blank{3}}{$(6)*6$} {Name of state variables in the saphyb object. This name is related to the record \moc{STATE$\_$VAR}: 1) control rod 2) density of moderator 3) boron concentration 4) temperature of fuel 5) temperature of moderator 6) burnup exposure.}
  
\CharEnr
 {STATE\_VAR\blank{3}}{$(N_{\rm pk})*4$} {Name of state variables (\moc{PKEY}).}

\CharEnr
 {ISOTOPES\blank{4}}{$(3)*12$} {Reference name of isotopes in the saphyb object for depletion chain, recovery of fission yield and number densities. 1) Xe135 2) I135 3) Sm 149.}
  
\RealEnr
 {\textit{/svname/}}{$N_{k}$}{ }
 {Values for each state variable specified by \moc{PKEY$_{k}$}, $N_{k}$ is the number of value taken for the k$^{th}$ PKEY. }  
 
    
\CharEnr
 {ADF\blank{9}}{$*3$} {Type of ADF recovered (\moc{GET} or \moc{SEL}).}
    
      
 \end{DescriptionEnregistrement}




\begin{DescriptionEnregistrement}{Records and sub-directories
 in \dir{HELIOS\_HEAD} }{7.0cm} \label{tabl:tabhel}

\RealEnr
 {FILE\_CONT\_1\blank{1}}{$2$}{ }
 {Set of data for \moc{FILE$\_$CONT$\_$1} block in \moc{DRA} file : Heavy metal Density(\moc{HM$\_$Dens}), Bypass Density(\moc{ByPass}). } 
  
\RealEnr
 {FILE\_CONT\_2\blank{1}}{$8$}{ }
 {Set of data for \moc{FILE$\_$CONT$\_$2} block in \moc{DRA} file : Lower Energy Limits of Neutron Groups. } 
  
\RealEnr
 {FILE\_CONT\_3\blank{1}}{$7$}{ }
 {Set of data for \moc{FILE$\_$CONT$\_$3} block in \moc{DRA} file : Volume of coolant (\moc{VCool}), moderator (\moc{VModr}), control rods (\moc{VCnRd}), fuel(\moc{VFuel}), cladding (\moc{VClad}), channels (\moc{VChan}), water (\moc{VWatR}). }
 
 \RealEnr
 {FILE\_CONT\_4\blank{1}}{$3$}{ }
 {Set of data for \moc{FILE$\_$CONT$\_$4} block in \moc{DRA} file : Cell Pitch and X,Y Position of First Cell. }
 
  \RealEnr
 {XS\_CONT\blank{6}}{$1$}{ }
 {Set of data for \moc{XS$\_$CONT} block in \moc{DRA} file :  (\moc{VFCM}). }
    
 \end{DescriptionEnregistrement}
 
 \begin{DescriptionEnregistrement}{Records and sub-directories
 in \dir{GENPMAXS\_INP} }{7.0cm} \label{tabl:tabgen}
\IntEnr
 {FLAG\blank{8}}{$1$}
 {Indicates the end of a branch calculation.} 
 
\CharEnr
 {JOB\_TIT\blank{5}}{$*16$}
 {Name of final PMAXS file. } 
  
\CharEnr
 {FILE\_NAME\blank{3}}{$*12$}
 {Name of output \moc{DRA} file } 
  
\CharEnr
 {DERIVATIVE\blank{2}}{$*4$}
 {Set of data for \moc{FILE$\_$CONT$\_$3} block in \moc{DRA} file : Volume of coolant (\moc{VCool}), moderator (\moc{VModr}), control rods (\moc{VCnRd}), fuel(\moc{VFuel}), cladding (\moc{VClad}), channels (\moc{VChan}), water (\moc{VWatR}). }
 
 \RealEnr
 {VERSION\blank{5}}{$1$}{ }
 {Version of PARCS used. }
 
  \CharEnr
 {COMMENT\blank{5}}{$*40$}
 {Free comment. }
    
\CharEnr
 {JOB\_OPT\blank{5}}{$(14)*1$}
 {Options for GenPMAXS running (see \cite{GENPMAXS}). }
 
 \RealEnr
 {DAT\_SRC\blank{5}}{$5$}{ }
 {Data source information (see \cite{GENPMAXS}). }
  
 \end{DescriptionEnregistrement}
 
Each component of the list \moc{TH$\_$DATA} is a directory containing TH data for a single burnup point. Inside each groupwise directory, the following records associated will be found:
 
 \begin{DescriptionEnregistrement}{Records 
 in sub-directory \dir{TH\_DATA} }{7.0cm} \label{tabl:tabTH}
 
 \OptRealEnr
 {CHI\blank{9}}{$N_{\rm gr}$} {$lchi$} { }
 {The steady-state energy spectrum of the neutron emitted by fission $\chi$. }
 
  \OptRealEnr
 {OVERV\blank{7}}{$N_{\rm gr}$}{$linv$} {s.cm$^{-1}$}
 {The average of the inverse neutron velocity. }
 
   \OptRealEnr
 {LAMBDA\blank{6}}{$N_{\rm del}$}{$lamb$} {s$^{-1}$}
 {Decay constant of delayed neutron. }
 
   \OptRealEnr
 {BETA\blank{8}}{$N_{\rm del}$}{$lbet$} {}
 {Effective delayed neutron fraction. }
  
   \OptRealEnr
 {YLDPm\blank{7}}{$1$}{$lyld$} { }
 { Effective yield value of Pm-149 }
 
    \OptRealEnr
 {YLDXe\blank{7}}{$1$}{$lyld$} { }
 { Effective yield value of Xe-135 }
 
     \OptRealEnr
 {YLDI\blank{8}}{$1$}{$lyld$} { }
 { Effective yield value of I-135 }

  
 \end{DescriptionEnregistrement} 
 
 
 \begin{DescriptionEnregistrement}{Records and sub-directories
 in sub-directory \dir{BRANCH\_INFO} }{7.0cm} \label{tabl:tabBR}
 
 \IntEnr
 {BRANCH\_IT\blank{3}}{$1$}
 {Index of the current branch type calculation.}
 
 \CharEnr
 {BRANCH\blank{6}}{$*4$}
 {Current BRANCH type calculation. } 
  
 \IntEnr
 {BRANCH\_NB\blank{3}}{$1$}
 {Number of branches to be created in PMAXS files.}  
 
 \RealEnr
 {REF\_STATE\blank{3}}{$N_{\rm pk}-1$}{ }
 {Values of state variables for reference state, burnup excepted. }
 
 \RealEnr
 {HST\_STATE\blank{3}}{$N_{\rm pk}-1$}{ }
 {Values of state variables for history state, burnup excepted. }
 
 \IntEnr
 {STATE\_INDEX\blank{1}}{$N_{\rm pk}$}
 {Current index value for each  state variables.}
 
 \IntEnr
 {BRANCH\_INDEX}{$N_{\rm pk}$}
 {Index of current  branch calculation.}
 
 \RealEnr 
 {STATE\blank{7}}{$N_{\rm pk}$}{ }
 {State variable values for the current branch  calculation. } 
 
 \IntEnr
 {REWIND\blank{6}}{$1$}
 {Indicates the end of a branch calculation (\moc{REWIND}=1).}
 
 \IntEnr
 {STOP\blank{8}}{$1$}
 {Indicates the end of calculation (\moc{STOP}=1).}
  
  
  \DirlEnr
 {CROSS\_SECT\blank{2}}{$N_{\rm bu}$}
 {Each component of the list is a directory containing cross sections for all  burnup point of a specific branch(cross sections are overwrited after each branch calcualtion).}  
 
  \OptDirlEnr
 {DIVERS\blank{6}}{$N_{\rm bu}$} {$I_{grid} \leq 1$}
 {Each component of the list is a directory containing the \moc{DIVERS} data block recovered from the saphyb object(inforamtions are overwrited after each branch calcualtion).}  
   
 \end{DescriptionEnregistrement} 
Each component of the list \moc{CROSS$\_$SECT} is a directory containing cross sections for all  burnup point of a specific branch. Cross sections for a single burnup points are filled seqentially during the branching calculation.  Inside each groupwise directory, the following sub-directories will be found:

 \begin{DescriptionEnregistrement}{Sub-directories
 in \dir{CROSS\_SECT} }{7.0cm} \label{tabl:tabXS}
  
  \DirEnr
 {MACROLIB\_XS\blank{1}}
 {Directory for macroscopic cross sections for a given calculated branch  (cross sections are overwrited after each branch calculation).}  
 
  \OptDirlEnr
 {MICROLIB\_XS\blank{1}}{} {$lxes$} 
 {Directory for microscopic cross sections for a given calculated branch (cross sections are overwrited after each branch calculation).}  
   
 \end{DescriptionEnregistrement} 
 
 
 \begin{DescriptionEnregistrement}{Records 
 in the sub-directory \dir{MACROLIB\_XS} }{7.0cm} \label{tabl:tabMA}
 
 \RealEnr
 {XTR\blank{9}}{$N_{\rm gr}$}{cm$^{-1}$}
 {The transport cross section $\Sigma^g_f$:
 $\Sigma^g_t = 1 / ( 3 \cdot D_{g} ) $. }
 
 \RealEnr
 {ABSORPTION\blank{2}}{$N_{\rm gr}$}{cm$^{-1}$}
 {The absorption cross section $\Sigma^g_a$: $\Sigma^g_a = \Sigma^g_{tot} - \sum_{g'} \Sigma^{g \rightarrow g'}_s $. }
 
 \RealEnr
 {KAPPA\_FI\blank{4}}{$N_{\rm gr}$}{cm$^{-1}$}
 {The product of $\Sigma^g_f$, the fission cross section with  the energy emitted by this reaction $\kappa$ :  $\kappa\Sigma^g_f$. }

 \RealEnr
 {X\_NU\_FI\blank{5}}{$N_{\rm gr}$}{cm$^{-1}$}
 {The product of $\Sigma^g_f$, the fission cross section with  the averaged number of fission–emitted delayed
neutron $\nu$ :  $\nu\Sigma^g_f$. }
 
 \RealEnr
 {SCAT\blank{8}}{$N_{\rm gr}*N_{\rm gr}$}{cm$^{-1}$}
 {Scattering cross section elements  from group g to g' : $\Sigma^{g \rightarrow g'}_s$. }
 
 \OptRealEnr
 {DET\blank{9}}{$N_{\rm gr}$} {$ldet$} { } 
 {The detector response parameter, it is product of cross section and local flux ratio. }
 
 \OptRealEnr
 {SFI\blank{9}}{$N_{\rm gr}$} {$lxes$} {cm$^{-1}$} 
 {The fission cross section : $\Sigma^g_f$. } 
 
 \OptRealEnr
 {ADF\blank{9}}{$N_{\rm adf},N_{\rm gr}$} {$ladf$} { }  
 { Assembly Discontinuity Factors. } 
  
 \end{DescriptionEnregistrement} 
 
  \begin{DescriptionEnregistrement}{Records 
 in the sub-directory \dir{MICROLIB\_XS} }{7.0cm} \label{tabl:tabMI}
 
 \OptRealEnr
 {XENG\blank{8}}{$N_{\rm gr}$} {} { cm$^{-2}$} 
 {The microscopic absorption cross section of Xenon: $\sigma^g_{a,Xe} = \sigma^g_{tot,Xe} - \sum_{g'} \Sigma^{g \rightarrow g'}_{s, Xe} $. }
 
 \OptRealEnr
 {SMNG\blank{8}}{$N_{\rm gr}$} {} {cm$^{-2}$ } 
 {The microscopic absorption cross section of Samarium: $\sigma^g_{a,Sm} = \sigma^g_{tot,Sm} - \sum_{g'} \Sigma^{g \rightarrow g'}_{s, Sm} $.}
 
  \OptRealEnr
 {XEND\blank{8}}{$N_{\rm gr}$} {} {(b.cm)$^{-1}$} 
 {The Xenon number density: $n_{Xe}$.}
 
  \OptRealEnr
 {SMND\blank{8}}{$N_{\rm gr}$} {} {(b.cm)$^{-1}$} 
 {The Samarium number density: $n_{Sm}$.}
  
 \end{DescriptionEnregistrement} 

Each component of the list \moc{DIVERS} is a directory containing informations for all  burnup points of a specific branch recovered from the \moc{DIVERS} block of the saphyb object. Inside each groupwise directory, the following records will be found:

  \begin{DescriptionEnregistrement}{Records 
 in the sub-directory \dir{DIVERS} }{7.0cm} \label{tabl:tabDI}
 
 \RealEnr
 {B2\blank{10}}{$1$} { cm$^{-2}$} 
 {Critical buckling. }
 
 \RealEnr
 {KEFF\blank{8}}{$1$} { } 
 {Effective multiplication factor. }
 
 \RealEnr
 {KINF\blank{8}}{$1$} { } 
 {Infinite multiplication factor. }
 
 \end{DescriptionEnregistrement} 

