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Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal

Abstract

This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These  More>>
Authors:
Publication Date:
Nov 10, 1998
Product Type:
Thesis/Dissertation
Report Number:
FRCEA-TH-713
Reference Number:
SCA: 220100; PA: AIX-30:035097; EDB-99:078622; SN: 99002122293
Resource Relation:
Other Information: DN: 70 refs.; TH: These Physique et modelisation des systemes complexes; PBD: 10 Nov 1998
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; A CODES; BOLTZMANN EQUATION; CRITICALITY; DISCRETE ORDINATE METHOD; FUEL CYCLE; M CODES; MONTE CARLO METHOD; MULTIGROUP THEORY; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; PERFORMANCE TESTING; REACTIVITY; T CODES; 220100; THEORY AND CALCULATION
OSTI ID:
10147144
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France). Lab. d`Etudes Neutroniques des Reacteurs; Universite de Provence, 13 - Marseille-1 (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Other: ON: DE99627815; TRN: FR9900720035097
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
208 p.
Announcement Date:

Citation Formats

Mattera, Ch. Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal. France: N. p., 1998. Web.
Mattera, Ch. Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal. France.
Mattera, Ch. 1998. "Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal." France.
@misc{etde_10147144,
title = {Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal}
author = {Mattera, Ch}
abstractNote = {This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author) 70 refs.}
place = {France}
year = {1998}
month = {Nov}
}