Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies

Redondo Valero, Elena ORCID: https://orcid.org/0000-0002-9842-0892, Queral Salazar, José Cesar ORCID: https://orcid.org/0000-0001-9384-2474, Fernández Cosials, Kevin ORCID: https://orcid.org/0000-0001-6722-1084, Sánchez Espinoza, Víctor Hugo, Sánchez Perea, Miguel and Groudev, Pavlin ORCID: https://orcid.org/0000-0002-3726-3678 (2024). Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies. "Progress in Nuclear Energy", v. 177 (n. 105414); ISSN 0149-1970. https://doi.org/10.1016/j.pnucene.2024.105414.

Descripción

Título: Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies
Autor/es:
Tipo de Documento: Artículo
Título de Revista/Publicación: Progress in Nuclear Energy
Fecha: Diciembre 2024
ISSN: 0149-1970
Volumen: 177
Número: 105414
Materias:
ODS:
Palabras Clave Informales: VVER-1000/V320; Westinghouse PWR; SBLOCA; Emergency operating procedures; Damage domains
Escuela: E.T.S.I. de Minas y Energía (UPM)
Departamento: Energía y Combustibles
Grupo Investigación UPM: Ciencia y Tecnología de sistemas avanzados de fisión nuclear
Licencias Creative Commons: Ninguna

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Resumen

In small break LOCA sequences with failure of the high-pressure safety injection system, the reactor coolant system pressure can stagnate at a high value making the medium and low-pressure safety injection systems unable to inject water into the core before its peak cladding temperature exceeds the safety limit. In this work, a review and comparison of different strategies presented in the Emergency Operating Procedures for managing these sequences in VVER-1000/V320 and Westinghouse PWR has been carried out. For this purpose, the Integrated Safety Assessment methodology, developed by the Spanish Nuclear Safety Council has been applied. The results show that the strategy related to the controlled SGs depressurization at a primary side cooling rate of 60 K/h in VVER-1000/V320 reactors and 55 K/h in Westinghouse PWR provides a wide safety margin. In cases where the Inadequate Core Cooling temperature is reached, the fast SGs depressurization strategy is also effective to avoid the core damage.

Proyectos asociados

Tipo
Código
Acrónimo
Responsable
Título
Gobierno de España
PID2019-108755RB-I00
ISASMORE
César Queral
Análisis integrado de seguridad de reactores modulares y Evolutivos

Más información

ID de Registro: 92814
Identificador DC: https://oa.upm.es/92814/
Identificador OAI: oai:oa.upm.es:92814
URL Portal Científico: https://portalcientifico.upm.es/es/ipublic/item/10249888
Identificador DOI: 10.1016/j.pnucene.2024.105414
URL Oficial: https://www.sciencedirect.com/science/article/pii/...
Depositado por: Doctor José César Queral Salazar
Depositado el: 13 Ene 2026 14:05
Ultima Modificación: 15 Ene 2026 19:59