Published December 17, 2004 | Version v1
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Multi-domain/Multi-method numerical approach for neutron transport equation

Creators

Description

A new methodology for the solution of the neutron transport equation, based on domain decomposition methods has been developed. This approach allows us to employ different numerical methods together for a whole core calculation: a variational nodal method, a discrete ordinate nodal method and a method of characteristics. These new developments authorize the use of independent spatial and angular expansion, non conformal Cartesian and unstructured meshes for each sub-domain, introducing a flexibility of modelization which is not allowed in today available codes. The effectiveness of our multi-domain-multi-method approach has been tested on several configurations. Among them, one particular application is the modelization of strong local heterogeneities, a realistic problem in the field of reactor physics. (author)

Abstract (French)

Une nouvelle methodologie pour la resolution de l'equation du transport, basee sur une methode de decomposition de domaine est developpee. Celle-ci permet l'utilisation simultanee de trois methodes de resolution differentes au sein du meme calcul: une methode variationnelle nodale, une methode aux ordonnees discretes et une methode des caracteristiques. Cette nouveaute se concretise par la possibilite d'employer des developpements spatiaux et angulaires differents, des maillages independants (cartesiens ou non-structures), voire non conformes, pour chaque sous-domaine de calcul, introduisant une flexibilite de modelisation qui n'est pas possible avec les codes de calcul disponibles actuellement. Les capacites de modelisation de l'approche multidomaine-multimethode sont demontrees au travers l'etude d'un probleme realiste de la physique des reacteurs: le calcul fin d'heterogeneites neutroniques localisees

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Additional details

Additional titles

Original title (French)
Couplage de methodes et decomposition de domaine pour la resolution de l'equation du transport des neutrons

Identifiers

URL
http://www.iaea.org/inis/Contacts/;

Publishing Information

Imprint Pagination
204 p.
Report number
FRCEA-TH--3300

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
43040683
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Thesis
Descriptors DEI
ANGULAR CORRELATION; BOLTZMANN EQUATION; CROSS SECTIONS; DISCRETE ORDINATE METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NEUTRONS; PHEBUS REACTOR; REACTOR CORES; VALIDATION
Descriptors DEC
BARYONS; CALCULATION METHODS; CORRELATIONS; DIFFERENTIAL EQUATIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; HADRONS; INTEGRO-DIFFERENTIAL EQUATIONS; KINETIC EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; POOL TYPE REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TESTING; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
66refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/
Secondary number(s)
CEA-R--6150