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Impact on the Sustainable Development Goals (SDGs)

Analysis of institutional authors

Queral CCorresponding AuthorFernández-Cosials KAuthorParis CAuthor

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January 22, 2021
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Application of Expanded Event Trees combined with uncertainty analysis methodologies

Publicated to: RELIABILITY ENGINEERING & SYSTEM SAFETY. 205 107246- - 2021-01-01 205(), DOI: 10.1016/j.ress.2020.107246

Authors:

Queral, Cesar; Fernandez-Cosials, Kevin; Zugazagoitia, Eneko; Paris, Carlos; Magan, Javier; Mendizabal, Rafael; Posada, Jose
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Affiliations

CNAT - Author
CNAT, Av Manoteras 46, Madrid 28050, Spain - Author
Consejo de Seguridad Nuclear - Author
Nucl Safety Council, Pedro Justo Dorado St, Madrid 28040, Spain - Author
Univ Politecn Madrid, Alenza 4 St, Madrid 28003, Spain - Author
Universidad Politécnica de Madrid - Author
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Abstract

© 2020 Elsevier Ltd During the last decades, the safety analysis of nuclear power plants, have been shifting from conservative models and hypotheses to Best Estimate. Within this trend, the different safety analyses can be categorized depending on their associated conservatisms. The approach that includes Expanded Event Trees together with Best Estimate model and conditions plus uncertainty avoiding conservatisms in system availability can be referred as Extended BEPU (EBEPU). In this sense, an Extended BEPU safety analysis relies on Expanded Event Trees and Best Estimate models to study an accidental sequence. In the present paper, an EBEPU study is performed, using a loss of coolant accident in a pressurized water reactor modeled with the TRACE code. A 5% core power uprate is used as an example of safety margin EBEPU analysis. The paper presents parametric and non-parametric uncertainty approaches. Observing the results from all event tree sequences, it is seen that the branches that contribute the most to the Core Damage frequency are successful branches, with all safety systems available, and some Core Damage branches have a possibility of success.
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Keywords

Clean water and sanitationExpanded event treesExtended bepuProbabilistic safety analysisTrace code

Quality index

Bibliometric impact. Analysis of the contribution and dissemination channel

The work has been published in the journal RELIABILITY ENGINEERING & SYSTEM SAFETY 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, 2021, it was in position 11/87, thus managing to position itself as a Q1 (Primer Cuartil), in the category Operations Research & Management Science.

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: 15
  • Scopus: 20
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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: 30 (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/92817/

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: 29
  • Downloads: 7
Continuing with the social impact of the work, it is important to emphasize that, due to its content, it can be assigned to the area of interest of ODS 6 - Clean water and sanitation, with a probability of 56% according to the mBERT algorithm developed by Aurora University.
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Leadership analysis of institutional authors

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 (QUERAL SALAZAR, JOSE CESAR) .

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

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Project objectives

La aportación persigue los siguientes objetivos: analizar la aplicación de los Árboles de Eventos Expandidos combinados con modelos Best Estimate para la evaluación de la seguridad en centrales nucleares; evaluar la metodología Extended BEPU (EBEPU) que integra análisis de incertidumbre evitando conservadurismos en la disponibilidad del sistema; determinar la efectividad de un estudio EBEPU mediante un accidente de pérdida de refrigerante en un reactor de agua presurizada modelado con el código TRACE; caracterizar el impacto de un aumento del 5% en la potencia del núcleo como ejemplo de análisis de margen de seguridad; y comparar enfoques paramétricos y no paramétricos de incertidumbre para identificar las secuencias de eventos que más contribuyen a la frecuencia de daño al núcleo.
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Most relevant results

Los resultados más relevantes del estudio se centran en la aplicación de árboles de eventos expandidos combinados con metodologías de análisis de incertidumbre en el análisis de seguridad nuclear. En primer lugar, se realizó un estudio EBEPU de un accidente por pérdida de refrigerante en un reactor de agua presurizada utilizando el código TRACE. En segundo lugar, se empleó un aumento del 5% en la potencia del núcleo como ejemplo para el análisis de márgenes de seguridad. En tercer lugar, se presentaron enfoques de incertidumbre paramétricos y no paramétricos. Finalmente, se observó que las ramas que más contribuyen a la frecuencia de daño al núcleo son las exitosas, con todos los sistemas de seguridad disponibles, y que algunas ramas con daño al núcleo presentan posibilidad de éxito.
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