Initial commit from Polytechnique Montreal

1 files changed, 76 insertions, 0 deletions

diff --git a/doc/IGE344/Intro.tex b/doc/IGE344/Intro.tex
new file mode 100644
index 0000000..2ab03b2
--- /dev/null
+++ b/doc/IGE344/Intro.tex
@@ -0,0 +1,76 @@
+\section{INTRODUCTION}\label{sect:intro}
+
+DONJON is a full-core modelization code designed around solution techniques of 
+the neutron diffusion or simplified $P_n$ equation.\cite{PIP2016}
+The current DONJON package is an evolution version, released as an attempt
+to introduce the innovative capabilities for the full-core modeling and simulations
+of different types of nuclear reactors sush as Pressurized Water Reactors (PWRs),
+legacy CANDU reactors, and Advanced CANDU Reactors (ACRs). The computer code DONJON (Release 4.0)
+is part of Version4 distribution\cite{v4}, implemented in Fortran-77, based on a 32-bit address
+space and containing modules that can be called from CLE-2000.\cite{cle2000}. The current DONJON
+package (DONJON Version5) is a rewrite of the code built around the Ganlib5 kernel, intended to
+be 64-bit clean.\cite{ganlib5}
+
+DONJON execution depends on other computer codes, components of Version4,
+namely: GANLIB, UTILIB, DRAGON\cite{dragon}, and TRIVAC\cite{trivac}
+codes. The DRAGON modules are used with DONJON code to define the reactor
+geometry, to provide the macroscopic cross-section libraries and to perform
+micro-depletion calculations. The TRIVAC
+solver modules are used to perform a spatial discretization of the reactor geometry
+and to provide the numerical solution according to the user-selected numerical
+procedure\cite{ah1,ah2,ah3,ah4,ah5,ah6}.
+The UTILIB library provides the utility and linear algebra libraries.
+Finally, the GANLIB computer code provides CLE-2000 capabilities to control
+data flows and to implement {\sl computational schemes}. GANLIB also provide
+LCM data structures to exchange information between modules.
+
+The DONJON code is divided into several modules, each module is designed
+to perform some particular tasks. The transfer of information between the modules
+is achieved by means of well defined data structure. Several design features,
+data structure and computing algorithms were recovered, revised and adapted
+from the previous DONJON version\cite{donjon,donjstruc}. One of the main
+concerns of the DONJON developers is to ensure the code reliability and extensibility.
+
+The DONJON modules are first designed for the reactor full-core modeling in
+\dusa{3-D} Cartesian geometry. These modules are built around the reactor fuel
+lattice specification corresponding to the common design features of CANDU
+reactors. The modules related to the modeling of reactivity mechanisms, which are
+normally presented in the reactor core, also constitute an important part of code.
+The DONJON code can perform several full-core calculations and can be used
+to determine some important core characteristics, such as the power and normalized
+flux distributions over the reactor core. All full-core calculations using current version
+of DONJON correspond to the reactor static conditions.
+
+The modeling of the reactor fuel lattice using DONJON is made in considering
+that the fuel lattice is composed of a well defined number of fuel channels and
+bundles. All reactor channels contain the same number of fuel bundles and are
+identified by their specific names. The fuel bundles have a distinct set of properties
+that are recovered and interpolated according to the specified global and local
+parameters. The interpolation of fuel properties with respect to burnup distribution
+can be performed according to the time-average or instantaneous models\cite{rozon}.
+The time-average calculation is performed in considering the bidirectional refuelling
+scheme of reactor channels and assuming that all channels have the same bundle-shift.
+
+The modeling of the reactivity mechanisms is based on their specified parameters,
+which include the devices position, rods insertion level, water filling level, direction
+of movement, etc. The rod-devices insertion level can be set according to their
+nominal positions or they can be displaced in and out of core. The devices can also
+be divided into several groups so that they can be manipulated, displaced or moved
+simultaneously. The time-dependent behaviour of the moving devices can be modeled
+and used for the transient simulations or reactor control studies. The reactivity worth
+of devices can also be studied and predicted using DONJON.
+
+The reactor material properties are essentially recovered from the reactor database,
+obtained from the lattice calculations using DRAGON code. The two distinct
+macroscopic cross-section libraries can be constructed using DONJON.
+The first \dds{macrolib} is constructed only for the material properties which
+are evolution-independent, such as reflector and devices properties. The second
+\dds{macrolib} is constructed only for the fuel properties, defined per each fuel
+bundle over the fuel lattice. The two libraries are next combined and updated,
+according to the devices insertion level. The produced extended \dds{macrolib}
+is subsequently used to obtain the numerical solution, using TRIVAC modules.
+
+Finally, it should be noted that the DONJON code development is permanently
+in progress. The future updates will provide several extended capabilities
+for the reactor design and calculations; they will be gradually added to the
+subsequent DONJON versions.