Published May 1983
| Version v1
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Adaptative numerical methods for transport problems in safety nuclear reactors by the use of perturbations signatures and processes
Description
The need for increasingly accurate nuclear reactor performance data has led to increasingly sophisticated methods for solving the Boltzmann transport equation. This work has revealed the need for analyzing the functional signatures of the neutron flux using pattern recognition techniques to relate the local and overall phases of reactor calculations according to the desired parameters. This approach makes it possible to develop procedures based on a reference calculations and designed to evaluate the disturbances due to changes in physical media and to media interface modifications
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
La necessite de connaitre toujours plus precisement les performances des reacteurs nucleaires de surete conduit a l'elaboration de methodes de resolution de l'equation de Boltzmann (ou equation du transport neutronique) toujours plus sophistiquees. Ces travaux font apparaitre la necessite d'une analyse des signatures (fonctionnelles du flux neutronique) par un procede de reconnaissance des formes afin de relier les etapes locales et globales du calcul du reacteur en fonction des parametres recherches. Cette approche permet l'elaboration de procedes de perturbations permettant, a partir d'un calcul de reference, d'evaluer les perturbations dues aux changements de milieux physiques et aux modifications d'interfaces de ces milieuxFiles
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Additional details
Additional titles
- Original title (French)
- Methodes numeriques adaptatives pour des problemes de transport dans les reacteurs nucleaires de surete par l'utilisation de signatures et de procedes de perturbations
Publishing Information
- Imprint Pagination
- 233 p.
- Report number
- FRNC-TH--1311
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 15013956
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- BOLTZMANN EQUATION; COLLISION INTEGRALS; COMPUTER CALCULATIONS; COUPLED REACTOR CORES; DISCRETE ORDINATE METHOD; DISTURBANCES; MANY-DIMENSIONAL CALCULATIONS; MESH GENERATION; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; PERTURBATION THEORY; PROBABILITY; RESEARCH AND TEST REACTORS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; EQUATIONS; INTEGRALS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR CORES; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- 54 refs.