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+\subsection{The \moc{MAC:} module}\label{sect:MACData}
+
+In DRAGON, the macroscopic cross sections associated with each mixture are
+stored in a \dds{macrolib} (as an independent data structure or as part of
+a \dds{microlib}) which may be generated using one of different ways:
+\begin{itemize}
+\item First, one can use directly the input stream already used for the remaining
+DRAGON data. In this case, a single macroscopic library is involved.
+\item The second method is via a GOXS format binary sequential
+file.\cite{MATXS} It should be noted that a number of GOXS files may be read
+successively by DRAGON and that it is possible to combine data from GOXS files
+with data taken from the input stream. One can also transfer the macroscopic cross sections to a
+GOXS format binary file if required. In this case, a single macroscopic library is involved.
+\item The third input method is through a file which already contains a \dds{macrolib}. In this
+case, two macroscopic and microscopic libraries are to be combined
+\item The fourth method consists to update an existing \dds{macrolib} using control-variable
+data recovered from a {\tt L\_OPTIMIZE} object.
+\end{itemize}
+
+The general format of the data for the \moc{MAC:} module is the following:
+\begin{DataStructure}{Structure \dstr{MAC:}} 
+$\{$ \dusa{MACLIB} \moc{:=} \moc{MAC:} $[$ \dusa{MACLIB} $]$ \moc{::} \dstr{descmacinp} \\
+\hspace*{0.2cm} $|$ \dusa{MICLIB} \moc{:=} \moc{MAC:} \dusa{MICLIB} \moc{::} \dstr{descmacinp} \\
+\hspace*{0.2cm} $|$ \dusa{MACLIB} \moc{:=} \moc{MAC:} $[$ \dusa{MACLIB} $]~[$ \dusa{OLDLIB} $]$ \moc{::} \dstr{descmacupd} \\
+\hspace*{0.2cm} $|$ \dusa{MACLIB} \moc{:=} \moc{MAC:} \dusa{MACLIB} \dusa{OPTIM} \\
+\hspace*{0.2cm} $\}$ \\
+\moc{;} 
+\end{DataStructure}
+
+\noindent
+The meaning of each of the terms above is:
+
+\noindent
+
+\begin{ListeDeDescription}{mmmmmmmm}
+
+\item[\dusa{MACLIB}] {\tt character*12} name of a \dds{macrolib} that will
+contain the macroscopic cross sections. If \dusa{MACLIB} appears on both LHS and
+RHS, it is updated; otherwise, it is created. If \dusa{MACLIB} is created, all
+macroscopic cross sections are first initialized to zero.
+
+\item[\dusa{MICLIB}] {\tt character*12} name of a \dds{microlib}. Only the
+\dds{macrolib} data substructure of this \dds{microlib} is then updated. This is
+used mainly to associate fixed sources densities with various mixtures. If any
+other cross section is modified for a specific mixture, the
+microscopic and macroscopic cross sections are no longer compatible. One can
+return to a compatible library using the library update module (see
+\Sect{LIBData}).
+
+\item[\dusa{OLDLIB}] {\tt character*12} name of a \dds{macrolib} or a \dds{microlib}
+which will be used to update or create the \dusa{MACLIB} \dds{macrolib}.
+
+\item[\dusa{OPTIM}] {\tt character*12} name of a {\tt L\_OPTIMIZE} object. The
+\dds{macrolib} \dusa{MACLIB} is updated using control-variable data recovered from \dusa{OPTIM}.
+
+\item[\dstr{descmacinp}] macroscopic input data structure for this module (see
+\Sect{descmacinp}).
+
+\item[\dstr{descmacupd}] macroscopic update data structure for this module (see
+\Sect{descmacupd}).
+
+\end{ListeDeDescription}
+
+\subsubsection{Input structure for module {\tt MAC:}}\label{sect:descmacinp}
+ 
+In the case where there are no \dusa{OLDLIB} specified, the \dstr{descmac} input structure takes
+the form:
+
+\begin{DataStructure}{Structure \dstr{descmacinp}}
+$[$ \moc{EDIT} \dusa{iprint} $]$ \\
+$[$ \moc{NGRO} \dusa{ngroup} $]$ \\
+$[$ \moc{NMIX} \dusa{nmixt} $]$ \\
+$[$ \moc{NIFI} \dusa{nifiss} $]$ \\
+$[$ \moc{DELP} \dusa{ndel} $]$ \\
+$[$ \moc{ANIS} \dusa{naniso} $]$ \\
+$[$ \moc{NADF} \dusa{nadf} $]$ \\
+$[$ \moc{CTRA} $\{$ \moc{NONE} $|$ \moc{APOL} $|$ \moc{WIMS} $|$ \moc{LEAK} $\}$ $]$ \\
+$[$ \moc{ALBP} \dusa{nalbp} ((\dusa{albedp}(ig,ia),ig=1,\dusa{ngroup}),ia=1,\dusa{nalbp}) $]$ \\
+$[$ \moc{WRIT} \dusa{GOXSWN} $]$ \\
+$[$ \moc{ENER} (\dusa{energy}(jg), jg=1,\dusa{ngroup} +1) $]$ \\
+$[$ \moc{VOLUME} (\dusa{volume}(ibm), ibm=1,\dusa{nmixt}) $]$ \\
+$[$ \moc{ADD} $]$ \\
+$[[$ $\{$	\moc{READ} $[$ (\dusa{imat}(i), i=1,\dusa{nmixt}) $]$ \dusa{GOXSRN} $[$ \moc{DELE} $]$
+$|$	 \moc{READ}  \moc{INPUT} $[[$ \dstr{descxs} $]]$ $\}$ $]]$ \\
+$[[$ \moc{STEP} \dusa{istep} \moc{READ} \moc{INPUT} $[[$ \dstr{descxs} $]]~]]$ \\
+$[$ \moc{NORM} $]$
+\end{DataStructure}
+
+\noindent with
+\begin{ListeDeDescription}{mmmmmmmm}
+
+\item[\moc{EDIT}] keyword used to modify the print level \dusa{iprint}.
+
+\item[\dusa{iprint}] index used to control the printing in this module.
+It must be set to 0 if no printing on the output file is required. The
+macroscopic cross sections can written to the output file if the
+variable \dusa{iprint} is greater than or equal to 2. The transfer cross
+sections will be printed if this parameter is greater than or equal to 3. The
+normalization of the transfer cross sections will be checked if \dusa{iprint}
+is greater than or equal to 5.
+
+\item[\moc{NGRO}] keyword to specify the number of energy groups for which
+the macroscopic cross sections will be provided. This information is required
+only if \dusa{MACLIB} is created and the cross sections are taken directly from
+the input data stream.
+
+\item[\dusa{ngroup}] the number of energy groups used for the calculations in
+DRAGON. The default value is \dusa{ngroup}=1. 
+
+\item[\moc{NMIX}] keyword used to define the number of material mixtures.
+This information is required only if \dusa{MACLIB} is created and the cross
+sections are taken directly from the input data stream or from a GOXS file.
+
+\item[\dusa{nmixt}] the maximum number of mixtures (a mixture is
+characterized by a distinct set of macroscopic cross sections) the 
+\dds{macrolib} may contain. The default value is \dusa{nmixt}=1.
+
+\item[\moc{NIFI}] keyword used to specify the maximum number of fissile
+spectrum associated with each mixture. Each fission spectrum generally
+represents a fissile isotope. This information is required only if \dusa{MACLIB}
+is created and the cross sections are taken directly from the input data stream.
+
+\item[\dusa{nifiss}] the maximum number of fissile isotopes per mixture. The
+default value is \dusa{nifiss}=1.
+
+\item[\moc{DELP}] keyword used to specify the number of delayed neutron groups.
+
+\item[\dusa{ndel}] the number of delayed neutron groups. The
+default value is \dusa{ndel}=0.
+
+\item[\moc{ANIS}] keyword used to specify the maximum level of anisotropy
+permitted in the scattering cross sections. This information is required only if
+\dusa{MACLIB} is created and the cross sections are taken directly from the
+input data stream.
+
+\item[\dusa{naniso}] number of Legendre orders for the representation of the
+scattering cross sections. The default value is \dusa{naniso}=1 corresponding to
+the use of isotropic scattering cross sections.
+
+\item[\moc{NADF}] keyword used to specify the number of averaged fluxes surrounding the geometry and used
+to compute {\sl assenbly discontinuity factors} (ADF).
+
+\item[\dusa{nadf}] number of averaged fluxes surrounding the geometry.
+
+\item[\moc{CTRA}] keyword to specify the type of transport correction that
+should be generated and stored on the \dds{macrolib}. The transport correction is to be
+substracted from the total and isotropic ($P_0$) within-group scattering cross sections. A leakage correction, equal 
+to the difference between current-- and flux--weighted total cross sections ($\Sigma_{1}-\Sigma_{0}$)
+is also applied in the \moc{APOL} and \moc{LEAK} cases. All the modules that
+will read this \dds{macrolib} will then have access to transport corrected
+cross sections. The default is no transport correction when the \dds{macrolib} is created from the
+input or GOXS files. 
+
+\item[\moc{NONE}] keyword to specify that no transport correction should be
+used in this calculation.
+
+\item[\moc{APOL}] keyword to specify that an APOLLO type transport correction
+based on the linearly anisotropic ($P_1$) scattering cross sections is to be set. This correction assumes that
+the micro-reversibility principle is valid for all energy groups. $P_1$ scattering
+information must exists in the {\sc macrolib}.
+
+\item[\moc{WIMS}] keyword to specify that a WIMS--type transport correction is used.
+The transport correction is recovered from a record named \moc{TRANC}. This
+record must exists in the {\sc macrolib}.
+
+\item[\moc{LEAK}] A leakage correction is applied to the total and
+$P_0$ within-group scattering cross sections. No transport correction is 
+applied in this case.
+
+\item[\moc{ALBP}] keyword used for the input of the multigroup physical albedo array.
+
+\item[\dusa{nalbp}] the maximum number of multigroup physical albedos. 
+
+\item[\dusa{albedp}] multigroup physical albedo array. 
+
+\item[\moc{WRIT}] keyword used to write cross section data to a GOXS file. In
+the case where \dusa{nifiss}$>$1, this option is invalid. 
+
+\item[\dusa{GOXSWN}] {\tt character*7} name of the GOXS file to be created or
+updated.
+
+\item[\moc{ENER}] keyword to specify the energy group limits.
+
+\item[\dusa{energy}] energy (eV) array which define the limits of the groups
+(\dusa{ngroup}+1 elements).  Generally \dusa{energy}(1) is the highest energy.
+
+\item[\moc{VOLUME}] keyword to specify the mixture volumes.
+
+\item[\dusa{volume}] volume (cm$^3$) occupied by each mixture.
+
+\item[\moc{ADD}] keyword for adding increments to existing macroscopic cross
+sections. In this case, the information provided in \dstr{descxs} represents
+incremental rather than standard cross sections. 
+
+\item[\moc{READ}] keyword to specify the input file format. One can use either
+the input stream (keyword \moc{INPUT}) or a GOXS format file. 
+
+\item[\dusa{imat}] array of mixture identifiers to be read from a GOXS file.
+The maximum number of identifiers permitted is  \dusa{nmixt} and the maximum
+value that \dusa{imat} may take is \dusa{nmixt}. When \dusa{imat} is 0, the
+corresponding mixture on the GOXS file is not included in the \dds{macrolib}. In the
+cases where \dusa{imat} is absent all the mixtures on the GOXS file are
+available in a DRAGON execution. They are numbered consecutively starting at 1
+or from the last number reached during a previous execution of the \moc{MAC:}
+module.
+
+\item[\dusa{GOXSRN}] {\tt character*7} name of the GOXS file to be read.
+
+\item[\moc{DELE}] keyword to specify that the GOXS file is deleted after being read
+
+\item[\moc{INPUT}] keyword to specify that mixture cross sections will be
+read on the input stream.
+
+\item[\dstr{descxs}] structure describing the format used for reading the
+mixture cross sections from the input stream (see
+\Sect{descxs}).
+
+\item[\moc{STEP}] keyword used to create a perturbation directory.
+
+\item[\dusa{istep}] the index of the perturbation directory.
+
+\item[\moc{NORM}] keyword to specify that the macroscopic scattering cross
+sections and the fission spectrum have to be normalized. This option is
+available even if the mixture cross sections were not read by the \moc{MAC:}
+module.
+
+\end{ListeDeDescription}
+
+\goodbreak
+
+\subsubsection{Macroscopic cross section definition}\label{sect:descxs}
+
+\begin{DataStructure}{Structure \dstr{descxs}}
+\moc{MIX} $[$ \dusa{matnum} $]$ \\
+\hskip 1.0cm $[~\{$ \moc{NTOT0} $|$ \moc{TOTAL} $\}$ (\dusa{xssigt}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{NTOT1} (\dusa{xssig1}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{TRANC} (\dusa{xsstra}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{NUSIGF} ((\dusa{xssigf}(jf,jg), jg=1,\dusa{ngroup}), jf=1,\dusa{nifiss}) $]$ \\
+\hskip 1.0cm $[$ \moc{CHI}    ((\dusa{xschi}(jf,jg),    jg=1,\dusa{ngroup}), jf=1,\dusa{nifiss})$]$ \\
+\hskip 1.0cm $[$ \moc{FIXE}   (\dusa{xsfixe}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{DIFF}   (\dusa{diff}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{DIFFX} (\dusa{xdiffx}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{DIFFY} (\dusa{xdiffy}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{DIFFZ} (\dusa{xdiffz}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{NUSIGD} (((\dusa{xssigd}(jf,idel,jg), jg=1,\dusa{ngroup}), idel=1,\dusa{ndel}), jf=1,\dusa{nifiss}) $]$ \\
+\hskip 1.0cm $[$ \moc{CHDL}   (((\dusa{xschid}(jf,idel,jg), jg=1,\dusa{ngroup}), idel=1,\dusa{ndel}), jf=1,\dusa{nifiss})$]$ \\
+\hskip 1.0cm $[$ \moc{OVERV} (\dusa{overv}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{NFTOT} (\dusa{nftot}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{FLUX-INTG} (\dusa{xsint0}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{FLUX-INTG-P1} (\dusa{xsint1}(jg), jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{H-FACTOR}   (\dusa{hfact}(jg),    jg=1,\dusa{ngroup}) $]$ \\
+\hskip 1.0cm $[$ \moc{SCAT} (( 
+    \dusa{nbscat}(jl,jg), \dusa{ilastg}(jl,jg),(\dusa{xsscat}(jl,jg,ig), \\
+\hskip 2.0cm     ig=1,\dusa{nbscat}(jl,jg) ), jg=1,\dusa{ngroup}), jl=1,\dusa{naniso}) $]$ \\
+\hskip 1.0cm $[[$ \moc{ADF} \dusa{hadf}  (\dusa{xadf}(jg),    jg=1,\dusa{ngroup}) $]]$
+\end{DataStructure}
+
+\begin{ListeDeDescription}{mmmmmmmm}
+
+\item[\moc{MIX}] keyword to specify that the macroscopic cross sections
+associated with a new mixture are to be read.
+
+\item[\dusa{matnum}] identifier for the next mixture to be read. The maximum
+value permitted for this identifier is \dusa{nmixt}. When \dusa{matnum} is
+absent, the mixtures are numbered consecutively starting with 1 or with the last
+mixture number read either on the GOXS or the input stream.  
+
+\item[\moc{NTOT0}] keyword to specify that the total macroscopic cross
+sections for this mixture follows.
+
+\item[\moc{TOTAL}] alias keyword for \moc{NTOT0}.
+
+\item[\dusa{xssigt}] array representing the multigroup total macroscopic cross
+section ($\Sigma^{g}$ in \xsunit) associated with this mixture.
+
+\item[\moc{NTOT1}] keyword to specify that the $P_1$--weighted total macroscopic cross
+sections for this mixture follows.
+
+\item[\dusa{xssig1}] array representing the multigroup $P_1$--weighted total macroscopic cross
+section ($\Sigma_1^{g}$ in \xsunit) associated with this mixture.
+
+\item[\moc{TRANC}] keyword to specify that the transport correction macroscopic cross
+sections for this mixture follows.
+
+\item[\dusa{xsstra}] array representing the multigroup transport correction macroscopic cross
+section ($\Sigma_{\rm tc}^{g}$ in \xsunit) associated with this mixture.
+
+\item[\moc{NUSIGF}] keyword to specify that the macroscopic fission cross
+section multiplied by the average number of neutrons per fission for this
+mixture follows.
+
+\item[\dusa{xssigf}] array representing the multigroup macroscopic fission
+cross section multiplied by the average number
+of neutrons per fission ($\nu\Sigma_{f}^{g}$ in \xsunit) for all the fissile
+isotopes associated with this mixture. 
+
+\item[\moc{CHI}] keyword to specify that the fission spectrum for this mixture
+follows.
+
+\item[\dusa{xschi}] array representing the multigroup fission spectrum
+($\chi^{g}$) for all the fissile isotopes associated with this mixture.
+
+\item[\moc{FIXE}] keyword to specify that the fixed neutron source density for
+this mixture follows.
+
+\item[\dusa{xsfixe}] array representing the multigroup fixed neutron source
+density for this mixture ($S^{g}$ in $s^{-1}cm^{-3}$). 
+
+\item[\moc{DIFF}] keyword to specify that the isotropic diffusion coefficient for
+this mixture follows.
+
+\item[\dusa{diff}] array representing the multigroup isotropic diffusion coefficient for
+this mixture ($D^{g}$ in $cm$). 
+
+\item[\moc{DIFFX}] keyword for input of the $X$--directed diffusion coefficient. 
+
+\item[\dusa{xdiffx}] array representing the multigroup $X$--directed diffusion coefficient ($D^g_x$ in cm) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{DIFFY}] keyword for input of the $Y$--directed diffusion coefficient. 
+
+\item[\dusa{xdiffy}] array representing the multigroup $Y$--directed diffusion coefficient ($D^g_y$ in cm) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{DIFFZ}] keyword for input of the $Z$--directed diffusion coefficient.
+
+\item[\dusa{xdiffz}] array representing the multigroup $Z$--directed diffusion coefficient ($D^g_z$ in cm) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{NUSIGD}] keyword to specify that the delayed macroscopic fission cross
+section multiplied by the average number of neutrons per fission for this
+mixture follows.
+
+\item[\dusa{xssigd}] array representing the delayed multigroup macroscopic fission
+cross section multiplied by the average number
+of neutrons per fission ($\nu\Sigma_{f}^{g,idel}$ in \xsunit) for all the fissile
+isotopes associated with this mixture. 
+
+\item[\moc{CHDL}] keyword to specify that the delayed fission spectrum for this mixture
+follows.
+
+\item[\dusa{xschid}] array representing the delayed multigroup fission spectrum
+($\chi^{g,idel}$) for all the fissile isotopes associated with this mixture.
+
+\item[\moc{OVERV}] keyword for input of the multigroup average of the inverse neutron velocity.
+
+\item[\dusa{overv}] array representing the multigroup average of the inverse neutron velocity ($<1/v>_{m}^g$) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{NFTOT}] keyword for input of the multigroup macroscopic fission cross sections.
+
+\item[\dusa{nftot}] array representing the multigroup macroscopic fission cross section ($\Sigma_{f}^g$) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{FLUX-INTG}] keyword for input of the multigroup $P_0$ volume-integrated fluxes.
+
+\item[\dusa{xsint0}] array representing the multigroup $P_0$ volume-integrated fluxes ($V\phi_0^g$) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{FLUX-INTG-P1}] keyword for input of the multigroup $P_1$ volume-integrated fluxes.
+
+\item[\dusa{xsint1}] array representing the multigroup $P_1$ volume-integrated fluxes ($V\phi_1^g$) for the mixture 
+\dusa{matnum}. 
+
+\item[\moc{H-FACTOR}] keyword to specify that the power factor for
+this mixture follows.
+
+\item[\dusa{hfact}] array representing the multigroup power factor for this
+mixture ($H^{g}$ in $eV~cm^{-1}$). 
+
+\item[\moc{SCAT}] keyword to specify that the macroscopic scattering cross
+section matrix for this mixture follows.
+
+\item[\dusa{nbscat}] array representing the number of primary groups ig with
+non vanishing macroscopic scattering cross section towards the secondary group jg
+considered for each anisotropy level associated with this mixture.
+
+\item[\dusa{ilastg}] array representing the group index of the most thermal
+group with non-vanishing macroscopic scattering cross section towards the
+secondary group jg considered for each anisotropy level associated with this
+mixture.
+
+\item[\dusa{xsscat}] array representing the multigroup macroscopic scattering
+cross section ($\Sigma_{sl}^{ig\to jg}$ in \xsunit) from the primary group ig
+towards the secondary group jg considered for each anisotropy level associated
+with this mixture. The elements are ordered using decreasing primary group
+number ig, from \dusa{ilastg} to (\dusa{ilastg}$-$\dusa{nbscat}$+1$), and an
+increasing secondary group number jg. Examples of input structures for 
+macroscopic scattering cross sections can be
+found in \Sect{ExXSData}.
+
+\item[\moc{ADF}] keyword to specify that the boundary flux information for this mixture follows.
+
+\item[\dusa{hadf}] character*8 type of a flux surrounding the geometry. The maximum number of types is equal to \dusa{nadf}.
+
+\item[\dusa{xadf}] array representing a multigroup flux of type \dusa{hadf} surrounding the geometry for this
+mixture. 
+
+\end{ListeDeDescription}
+
+\subsubsection{Update structure for operator {\tt MAC:}}\label{sect:descmacupd}
+ 
+In the case where \dusa{OLDLIB} is specified, the \dstr{descmacupd} input structure takes
+the form:
+
+\begin{DataStructure}{Structure \dstr{descmacupd}}
+$[$ \moc{EDIT} \dusa{iprint} $]$ \\
+$[$ \moc{NMIX} \dusa{nmixt} $]$ \\
+$[$ \moc{CTRA} \moc{OFF} $]$ \\
+$[[$ \moc{MIX} \dusa{numnew} $[$ \dusa{numold} $\{$ \moc{UPDL} $|$ \moc{OLDL} $\}$ $]$ $]]$
+\end{DataStructure}
+
+\noindent with
+\begin{ListeDeDescription}{mmmmmm}
+
+\item[\moc{EDIT}] keyword used to modify the print level \dusa{iprint}.
+
+\item[\dusa{iprint}] index used to control the printing in this operator.
+It must be set to 0 if no printing on the output file is required. The
+macroscopic cross sections can written to the output file if the
+variable \dusa{iprint} is greater than or equal to 2. The transfer cross
+sections will be printed if this parameter is greater than or equal to 3. The
+normalization of the transfer cross sections will be checked if \dusa{iprint}
+is greater than or equal to 5.
+
+\item[\moc{NMIX}] keyword used to define the number of material mixtures.
+This information is required only if \dusa{MACLIB} contains more mixtures than \dusa{OLDLIB}.
+
+\item[\dusa{nmixt}] the maximum number of mixtures (a mixture is
+characterized by a distinct set of macroscopic cross sections) \dusa{MACLIB}
+may contain.
+
+\item[\moc{CTRA}] keyword to specify the type of transport correction that
+should be generated and stored on the \dds{macrolib}. All the operators that
+will read this \dds{macrolib} will then have access to transport corrected
+cross sections. In the case where the \dds{macrolib} is updated using other
+\dds{macrolib} or \dds{microlib} the default is to use a transport correction whenever one of these
+older data structure requires a transport correction.
+
+\item[\moc{OFF}] deactivates the transport correction.
+
+\item[\moc{MIX}] keyword to specify that the macroscopic cross sections
+associated with a mixture is to be created or updated.
+
+\item[\dusa{numnew}] mixture number to be updated or created on the output
+\dds{macrolib}. 
+
+\item[\dusa{numold}] mixture number on an old \dds{macrolib} or \dds{microlib} which will be used
+to update or create \dusa{numnew} on the output macrolib 
+
+\item[\moc{OLDL}] the
+macroscopic cross sections associated with mixture \dusa{numold} are taken from \dusa{OLDLIB}. This is the
+default option.
+
+\item[\moc{UPDL}] the
+macroscopic cross sections associated with mixture \dusa{numold} are taken from \dusa{MACLIB}.
+
+\end{ListeDeDescription}
+
+\eject