Lessons Learned and Best Practices on BWR Severe Accident Uncertainty and Sensitivity Analysis in the Framework of the IAEA CRP I31033
Rattachement africain : mx, Ghana, it. Niveau de preuve : code pays fourni par la source.
Le résumé fourni par la source
The International Atomic Energy Agency (IAEA) launched Coordinated Research Project (CRP) I31033, “Advancing the State-of-Practice in Uncertainty and Sensitivity Methodologies for SA Analysis in Water-Cooled Reactors,” in 2019. One of the main outputs of this CRP was a series of technical documents (TECDOCs) presenting the methodologies for performing uncertainty and sensitivity analysis developed by each of the 22 participating institutions and applied to different water-cooled reactors, i.e. pressurized water reactors (including small modular reactors), boiling water reactors (BWRs), CANDUs, and VVERs, as well as the QUENCH-06 experiment.This paper presents the BWR group´s main outcomes from this CRP and the contents of the TECDOC in preparation, including best practices and lessons learned by the four organizations contributing to the TECDOC: (1) CIEMAT (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas), (2) GAEC (Ghana Atomic Energy Commission), (3) CNSNS (Comisión Nacional de Seguridad Nuclear y Salvaguardias), and (4) ININ (Instituto Nacional de Investigaciones Nucleares). The first two institutions addressed severe accident scenarios in a BWR/3 with Mark-I primary containment, while the last two used models of a BWR/5 with Mark-II containment.Except for CNSNS, the participants chose a short-term (unmitigated) station blackout scenario for analysis, and the scope of the analysis was limited to only in-vessel phenomena. In the case of CNSNS, depressurization and reactor core isolation cooling injection were considered mitigating measures, and the analysis included both in-vessel and ex-vessel phenomena.The MELCOR code was used by the first three participants, and the MAAP5 code was used by ININ. Information on the figures of merit and the set of uncertain code input variables with their associated probability density functions is also presented in this paper.
Ce résumé expose les affirmations des auteurs. BNTIC ne l’interprète pas comme une validation indépendante des résultats.
Le contrôle bibliographique ouvert
DOI retrouvé dans Crossref DOI retrouvé ; titre concordant.
- Titre Crossref
- Lessons Learned and Best Practices on BWR Severe Accident Uncertainty and Sensitivity Analysis in the Framework of the IAEA CRP I31033
- Date Crossref
- 26/06/2025
- Éditeur
- Informa UK Limited
- Type
- journal-article
Ce recoupement confirme des métadonnées liées au DOI. Il ne confirme ni la méthode ni les conclusions de l’étude, et il ne compte pas comme une seconde source scientifique indépendante.
Où se fait cette recherche
-
Instituto Nacional de Investigaciones Nucleares pays non établi dans la noticeStructure de recherche
-
Ghana Atomic Energy Commission Ghana (code pays fourni par la source)Organisation à but non lucratif
-
National Agency for New Technologies pays non établi dans la noticeOrganisme public
-
National Nuclear Research Institute Ghana Atomic Energy Commission Legon, Ghana (pays nommé dans l’affiliation)Structure de recherche
-
Centre for Research on Energy pays non établi dans la noticeInstitution
-
Comisión Nacional de Seguridad Nuclear y Salvaguardias pays non établi dans la noticeInstitution
-
Agenzia Nazionale per le Nuove Tecnologie pays non établi dans la noticeInstitution
-
International Atomic Energy Agency pays non établi dans la noticeOrganisme public
Instituto Nacional de Investigaciones Nucleares, Ghana Atomic Energy Commission (Ghana) et National Agency for New Technologies, avec 5 autres affiliations. Pays d’affiliation : Ghana.
Une affiliation ne permet pas de déduire la nationalité d’un auteur.