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Analysis of institutional authors

Redondo-Valero, ElenaAuthorQueral, CesarCorresponding AuthorFernandez-Cosials, KevinAuthor

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September 22, 2024
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Management of the SBLOCA sequences with HPIS failure in VVER-1000/ V320 reactors; comparison with Westinghouse PWR strategies

Publicated to: PROGRESS IN NUCLEAR ENERGY. 177 105414- - 2024-12-01 177(), DOI: 10.1016/j.pnucene.2024.105414

Authors:

Redondo-Valero, Elena; Queral, Cesar; Fernandez-Cosials, Kevin; Sanchez-Espinoza, Victor Hugo; Sanchez-Perea, Miguel; Groudev, Pavlin
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Affiliations

Bulgarian Acad Sci, Inst Nucl Res & Nucl Energy, Tzarigradsko Shaussee 72, BU-1784 Sofia, Bulgaria - Author
Consejo Segur Nucl CSN, Pedro Justo Dorado Dellmans 11, Madrid 28040, Spain - Author
Karlsruhe Inst Technol KIT, Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany - Author
Univ Politecn Madrid UPM, Ramiro de Maeztu 7, Madrid 28040, Spain - Author
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Abstract

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.
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Keywords

Damage domainDamage domainsDynamic event treesEmergency operating proceduresHpsLocaRcp tripSblocaSuccess criteriaValidationVver-1000/v320Westinghouse pwr

Quality index

Bibliometric impact. Analysis of the contribution and dissemination channel

The work has been published in the journal PROGRESS IN NUCLEAR ENERGY due to its progression and the good impact it has achieved in recent years, according to the agency WoS (JCR), it has become a reference in its field. In the year of publication of the work, 2024 there are still no calculated indicators, but in 2023, it was in position 4/41, thus managing to position itself as a Q1 (Primer Cuartil), in the category Nuclear Science & Technology. Notably, the journal is positioned above the 90th percentile.

Independientemente del impacto esperado determinado por el canal de difusión, es importante destacar el impacto real observado de la propia aportación.

Según las diferentes agencias de indexación, el número de citas acumuladas por esta publicación hasta la fecha 2026-04-24:

  • WoS: 2
  • Scopus: 5
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Impact and social visibility

From the perspective of influence or social adoption, and based on metrics associated with mentions and interactions provided by agencies specializing in calculating the so-called "Alternative or Social Metrics," we can highlight as of 2026-04-24:

  • The use of this contribution in bookmarks, code forks, additions to favorite lists for recurrent reading, as well as general views, indicates that someone is using the publication as a basis for their current work. This may be a notable indicator of future more formal and academic citations. This claim is supported by the result of the "Capture" indicator, which yields a total of: 3 (PlumX).

It is essential to present evidence supporting full alignment with institutional principles and guidelines on Open Science and the Conservation and Dissemination of Intellectual Heritage. A clear example of this is:

  • Assignment of a Handle/URN as an identifier within the deposit in the Institutional Repository: https://oa.upm.es/92814/

As a result of the publication of the work in the institutional repository, statistical usage data has been obtained that reflects its impact. In terms of dissemination, we can state that, as of

  • Views: 37
  • Downloads: 69
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Leadership analysis of institutional authors

This work has been carried out with international collaboration, specifically with researchers from: Bulgaria; Germany.

There is a significant leadership presence as some of the institution’s authors appear as the first or last signer, detailed as follows: First Author (REDONDO VALERO, ELENA) .

the author responsible for correspondence tasks has been QUERAL SALAZAR, JOSE CESAR.

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Project objectives

Este trabajo persigue los siguientes objetivos: analizar las secuencias de pequeña pérdida de refrigerante (SBLOCA) con fallo del sistema de inyección de alta presión en reactores VVER-1000/V320; comparar las estrategias de gestión de estas secuencias en reactores VVER-1000/V320 y Westinghouse PWR; aplicar la metodología Integrated Safety Assessment desarrollada por el Consejo de Seguridad Nuclear español para evaluar dichas estrategias; determinar la eficacia de la estrategia de despresurización controlada de generadores de vapor con tasas de enfriamiento primario de 60 K/h en VVER-1000/V320 y 55 K/h en Westinghouse PWR; y evaluar la efectividad de la estrategia de despresurización rápida de generadores de vapor para evitar daños en el núcleo cuando se alcanza la temperatura de refrigeración inadecuada.
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Most relevant results

Los resultados más relevantes del estudio se centran en la gestión de secuencias SBLOCA con fallo del sistema de inyección de alta presión en reactores VVER-1000/V320 y PWR Westinghouse. En primer lugar, la estrategia de despresurización controlada de los generadores de vapor (SG) a una tasa de enfriamiento primaria de 60 K/h en VVER-1000/V320 y 55 K/h en PWR Westinghouse proporciona un amplio margen de seguridad. En segundo lugar, cuando se alcanza la temperatura de enfriamiento inadecuado del núcleo, la estrategia de despresurización rápida de los SG resulta eficaz para evitar daños en el núcleo. Finalmente, la metodología Integrated Safety Assessment aplicada permite comparar y validar estas estrategias operativas en ambos tipos de reactores.
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Awards linked to the item

This work in the framework of the Grant PID2019-108755RB-I00 (ISASMORE) funded by MCIN/AEI/10.13039/501100011033. The authors want also thanks to CAMP-Spain project, PC2006480221, its support.
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