Safety Analysis Reports of First-Of-A-Kind Nuclear Reactors in Brazil: Proposal of Content for Deterministic Safety Analysis

Authors

  • Nelson Luiz Dias Ferreira Diretoria de Desenvolvimento Nuclear da Marinha
  • Claudia Giovedi Motta Diretoria de Desenvolvimento Nuclear da Marinha (DDNM)
  • Mike Modro Nuclear and INdustrial Engineering (N.IN.E)
  • Alessandro Petruzzi Nuclear and INdustrial Engineering (N.IN.E)

DOI:

https://doi.org/10.15392/2319-0612.2024.2740

Keywords:

Licensing, safety analysis report, deterministic safety analysis

Abstract

The main documents of Licensing processes for nuclear reactors in Brazil are the Preliminary Safety Analysis Report (PSAR), in the construction phase, and the Final Safety Analysis Report (FSAR), in the operation phase (initial and permanent), as defined by the National Nuclear Energy Commission (CNEN). Thus, this paper presents a proposal for the format and content of the Deterministic Safety Analysis (DSA) chapter of Safety Analysis Reports (SAR) of First-Of-A-Kind (FOAK) nuclear reactors in Brazil, such as Small Modular Reactors (SMR), based on the combination of recommendations of United States Nuclear Regulatory Commission (USNRC) and International Atomic Energy Agency (IAEA) normative and documentary basis. Documentation from the USNRC applies to Nuclear Power Plants (NPPs), specifically to Light Water Reactors (LWR); complementary, IAEA documentation outlines a format and content of a SAR for NPPs but it may, in parts, have a wider applicability to other nuclear facilities. Compared to what is recommended by the USNRC, the IAEA allows for greater scope in terms of the types of events to be considered in a DSA, such as, for example, the Design Extension Conditions (DEC) and, in terms of methodology, it allows for a greater number of options for DSA approaches. The content proposal presented in this work recommends the consideration of DEC without significant fuel degradation (DEC-A), the adoption of the combined approach, analysis of hazards and Pressurized Thermal Shocks (PTSs) analysis, among others.

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Author Biography

  • Nelson Luiz Dias Ferreira, Diretoria de Desenvolvimento Nuclear da Marinha

    Departamento de Licenciamento e Análise de Segurança

    Divisão de Licenciamento Técnico

References

Comissão Nacional de Energia Nuclear. CNEN NE 1.04: Licenciamento de Instalações Nucleares, CNEN, Resolução CNEN 324/24, Rio de Janeiro, 2024.

United States Nuclear Regulatory Commission (USNRC). Regulatory Guide 1.70: Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, rev. 3, USNRC, Washington, 1978.

United States Nuclear Regulatory Commission (USNRC). Regulatory Guide 1.206: Combined License Applications for Nuclear Power Plants, rev. 0, USNRC, Washington, 2007.

United States Nuclear Regulatory Commission (USNRC). NUREG-0800: Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition, USNRC, Washington, 2016.

International Atomic Energy Agency. SSG-61: Format and Content of the Safety Analysis Report for Nuclear Power Plants, IAEA, Vienna, 2021.

International Atomic Energy Agency. SSG-2 (Rev. 1): Deterministic Safety Analysis for Nuclear Power Plants, IAEA, Vienna, 2019.

International Atomic Energy Agency. SSR-2/1 (Rev. 1): Safety of Nuclear Power Plants: Design, IAEA, Vienna, 2016.

International Atomic Energy Agency. GSR Part 4 (Rev. 1): Safety Assessment for Facilities and Activities, IAEA, Vienna, 2016.

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Published

2025-02-12

How to Cite

Safety Analysis Reports of First-Of-A-Kind Nuclear Reactors in Brazil: Proposal of Content for Deterministic Safety Analysis. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 12, n. 4B (Suppl.), p. e2740, 2025. DOI: 10.15392/2319-0612.2024.2740. Disponível em: https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/2740. Acesso em: 1 may. 2025.