Published 2022 | Version v1
Book

APOLLO3 calculation of BWR fuel assembly of a burn-up credit criticality benchmark

  • 1. Grenoble Institute of Technology, Department of Nuclear Energy Engineering, 38031, Grenoble (France)
  • 2. Universite Paris-Saclay, Service d'Etudes des Reacteurs et de Mathematiques Appliquees - SERMA, 91191 Gif-sur-Yvette (France)

Description

The article presents the results obtained by APOLLO3 on the Phase III-C benchmark problem. The paper demonstrates the capability of APOLLO3 to perform accurate burn-up calculations of a BWR assembly. The neutron transport equation is solved using the Method Of Characteristics in space with tracking data for angular discretization. The calculation also uses recently developed tools to automate input creation, validation, and post-treatment, such as ALAMOS and TriAGe. Then we presented a mesh convergence analysis through the study of the infinite multiplication factor k, production, and absorption reaction rates. The comparison of our validation with two other participants highlights the quality of our results. Finally a comparison of our results among other benchmark participants is detailed despite the large dispersion of k published

Availability note (English)

Available (CD Rom) from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)
Part of:
Proceedings of the international conference on physics of reactors - Physor 2022

Additional details

Publishing Information

Publisher
ANS - American Nuclear Society
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-787-3
Imprint Title
Proceedings of the international conference on physics of reactors - PHYSOR 2022
Imprint Pagination
3701 p.
Journal Page Range
p. 3660-3669

Conference

Title
International conference on physics of reactors
Acronym
PHYSOR 2022
Dates
15-20 May 2022
Place
Pittsburg (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
54042223
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
A CODES; BENCHMARKS; BURNUP; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; NEUTRON TRANSPORT THEORY; VALIDATION
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 refs.