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)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.