External Events PSA – Requirements Applicable to New Nuclear Installations Projects after Fukushima Daiichi Accident

Authors

  • T. P. Silva Centro Tecnológico da Marinha em São Paulo
  • M. C. Maturanaa Centro Tecnológico da Marinha em São Paulo
  • P. S. P. de Oliveira Instituto de Pesquisas Energéticas e Nucleares
  • M. Mattar Neto Instituto de Pesquisas Energéticas e Nucleares

DOI:

https://doi.org/10.15392/2319-0612.2022.1977

Keywords:

Probabilistic Safety Analysis, External events, Nuclear safety

Abstract

Since the Fukushima Daiichi accident, external events analysis has become a priority issue within regulatory bodies, operators, and designers, raising concerns about the capabilities of nuclear power plants to withstand severe conditions.

Generally, the methodology applied to the Probabilistic Safety Assessment (PSA) of external events consists of the identification of potential single and combined external hazards, screening of external hazards, analysis of site and plant response, analysis of initiating events and quantification of accident sequences probabilities.

Therefore, in this paper, the requirements and other information on new nuclear installations projects necessary to implement a comprehensive PSA of external events throughout plant lifetime are evaluated.

In addition, it is necessary to clearly identify all the resources that must be available to continuously expand PSA scope to include all types of initiating events, levels of analysis and plant operation modes.

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References

IAEA – International Atomic Energy Agency. IAEA Safety Glossary – Terminology used in nuclear safety and radiation protection 2018 edition. IAEA Safety Glossary, Vienna, 2018.

EPRI – Electric Power Research Institute. Identification of external hazards for analysis in probabilistic risk assessment. EPRI Report 3002005287 Update of Report 1022997, USA, 2015.

SKI – Swedish Nuclear Inspectorate. Guidance for external events analysis. SKI Report 02:27, Sweden, 2003.

U.S. NRC – United States Nuclear Regulatory Commission. An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities. U.S. NRC Regulatory guide 1.200, USA, 2009

IAEA – International Atomic Energy Agency. Modelling and data prerequisites for specific applications of PSA in the management of nuclear plant safety. IAEA-TECDOC-740, Vienna, 1994

CNEN – Comissão Nacional de Energia Nuclear. Licenciamento de Instalações Nucleares. Norma CNEN NE 1.04, Brasil, 2002.

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Published

2022-01-19

How to Cite

Silva, T. P., Maturanaa, M. C., Oliveira, P. S. P. de, & Mattar Neto, M. (2022). External Events PSA – Requirements Applicable to New Nuclear Installations Projects after Fukushima Daiichi Accident. Brazilian Journal of Radiation Sciences, 10(3A (Suppl.). https://doi.org/10.15392/2319-0612.2022.1977

Issue

Section

INAC 2021_XXII ENFIR_VII_ENIN

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