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/Intro.tex | 76 ++++++++++++++++++++++++++++++++++++++++++++++++++++ 1 file changed, 76 insertions(+) create mode 100644 doc/IGE344/Intro.tex (limited to 'doc/IGE344/Intro.tex') 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. -- cgit v1.2.3