Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2

Abstract. A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On the one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results from analyses by reactor utilities and regulators is very complex. The process is also highly dependent upon mandatory approaches pursued for the analysis and from very many details which required the knowledge of sensitive proprietary data (e.g. spacer designs). Furthermore, all data available for the design, construction and operation of reactors produced by the nuclear industry are available to regulators. Two areas for improving the process of safety assessment for individual Nuclear Power Plant Units are identified: New details introduced by industry are not always and systematically requested by regulators for the independent assessment; New analytical techniques and capabilities are not necessarily used in the analyses by regulators (and by the industry). The established concept of independent assessment constitutes the way for improving the process of safety assessment. This is possible, or is largely facilitated, by the recent availability of the so-called Best Estimate Plus Uncertainty approach.

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“…-BEPU implies the integration between Deterministic and Probabilistic Safety Analysis, i.e. DSA and PSA, respectively [6].…”

Section: The Features Of the Bepu Approachmentioning

confidence: 99%

Independent assessment for new nuclear reactor safety

D'Auria

Glaeser²,

Debrecin

2017

EPJ Nuclear Sci. Technol.

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“…Option 4, which is also called realistic deterministic safety analysis, is currently under research. An area of research in this context aims at developing methods for combining insights from probabilistic and deterministic safety analyses [7,8]. The new methods, such as the one presented in [8], are intended to be used for safety assessment of some current NPP DBC, which includes anticipated occupational occurrences, also called DBC-2 (faults of moderate frequency), and DEC, both without and with significant fuel degradation, which are also called DEC-A and DEC-B accidents respectively.…”

Section: Accepted M M a N U mentioning

confidence: 99%

An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses

Martorell

Sánchez-Saez

Sancho

et al. 2017

Reliability Engineering & System Safety

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This is a PDF file of an unedited manuscript that has been accepted for publication. As a service to our customers we are providing this early version of the manuscript. The manuscript will undergo copyediting, typesetting, and review of the resulting proof before it is published in its final form. Please note that during the production process errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain. Highlights  Option 4 Deterministic Safety Analysis  Best Estimate Plus Uncertainty (BEPU) methodology  Extended BEPU  Realistic safety systems configurations  PSA-based configurations

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“…El enfoque EBEPU está todavía en una fase de desarrollo preliminar y todavía no se han realizado muchos estudios bajo las premisas de la opción 4 de la SSG.2 (IAEA, 2009). Una de las propuestas más destacadas hasta la fecha, a partir de la cual se va a proponer una metodología EBEPU en esta Tesis, es la realizada por (Dusic, et al, 2014). En ella, se exponen con detalle los pasos a seguir por la metodología propuesta por los autores y se proporcionan algunos ejemplos de aplicación, desde el punto de vista teórico.…”

Section: Análisis Determinista De Seguridad Con Metodología Ebepuunclassified

Aportaciones Al Análisis Determinista De Seguridad Del Las Centrales Nucleares Mediante Metodología Best Estimate

Sáez¹

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Antes que nada, me gustaría dar las gracias a mis directores de Tesis Sebastián Martorell Alsina y Sofia Carlos Alberola, por su ayuda, dedicación y confianza en mí, porque sin su apoyo y motivación no habría podido realizar esta tesis. Trabajar con ellos es un placer. Per últim, a la present Tesi es proposa una metodologia per a incorporar les suposicions, pròpies del APS en quant a la configuració dels sistemes de seguretat dins del ADS. D'aquesta forma, s'obté una aproximació emmarcada dins de les metodologies conegudes com Extended BEPU (EBEPU). Per demostrar la viabilitat i aplicabilitat d'aquesta metodologia, s'aporta un cas d'aplicació que consisteix en la pèrdua d'aigua d'alimentació (LOFW) en una CN de tipus PWR.

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Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2

Cited by 22 publications

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Independent assessment for new nuclear reactor safety

Independent assessment for new nuclear reactor safety

An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses

Aportaciones Al Análisis Determinista De Seguridad Del Las Centrales Nucleares Mediante Metodología Best Estimate

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