Texto completo
|
PDF (Portable Document Format)
- Se necesita un visor de ficheros PDF, como GSview, Xpdf o Adobe Acrobat Reader
Descargar (3MB) |
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.
| 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 |
|
PDF (Portable Document Format)
- Se necesita un visor de ficheros PDF, como GSview, Xpdf o Adobe Acrobat Reader
Descargar (3MB) |
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.
| 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 |
Publicar en el Archivo Digital desde el Portal Científico