From 7dfcc480ba1e19bd3232349fc733caef94034292 Mon Sep 17 00:00:00 2001
From: stainer_t <thomas.stainer@oecd-nea.org>
Date: Mon, 8 Sep 2025 13:48:49 +0200
Subject: Initial commit from Polytechnique Montreal

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 doc/IGE369/Summary.tex | 34 ++++++++++++++++++++++++++++++++++
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+\clearpage
+$ $
+\vskip 2.0cm
+
+\begin{center}
+
+SUMMARY
+
+\end{center}
+
+TRIVAC is a computer code intended to compute the neutron flux in a 
+fractional or in a full core representation of a nuclear reactor. Interested readers
+can obtain fundamental informations about full-core calculations in Chapter~5
+of Ref.~\citen{PIP2009}. The multigroup
+and multidimensional form of the diffusion equation or simplified $P_n$ equation
+is first discretized to
+produce a consistent matrix system. This matrix system is subsequently solved
+using iterative techniques (inverse or preconditioned power method with
+ADI preconditioning) and sparse matrix algebra techniques
+(triangular factorization). The actual implementation of TRIVAC allows the
+discretization of 1-D geometries (slab and cylindrical), 2-D geometries
+(Cartesian, cylindrical and hexagonal) and 3-D geometries (Cartesian and
+hexagonal). Many discretization techniques are available, including mesh corner
+or mesh centered finite difference methods, collocation techniques of various
+order and finite element methods based on a primal or dual functional
+formulation. TRIVAC also permits  the equations of the generalized
+perturbation theory (GPT) to be solved as fixed source eigenvalue problems.
+Finally, several implicit numerical schemes are available for the solving of space-time
+neutron kinetics problems.
+
+\vskip 0.15cm
+
+The execution of TRIVAC is controlled by CLE-2000.\cite{cle2000} It is
+modular and can be interfaced easily with other production codes.
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