Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal

Authors

  • Raíssa Oliveira Marques Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN
  • Vanderley Vasconcelos Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN
  • Wellington Antonio Soares Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN
  • Silvério Ferreira Silva Júnior Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN
  • Amanda Laureano Raso Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN
  • Amir Zacarias Mesquita Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN

DOI:

https://doi.org/10.15392/bjrs.v8i3B.371

Keywords:

RBI, PSA, nuclear research reactors

Abstract

Industrial facilities systems deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core and allow changes in fuel configurations. Ageing management of components is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration is considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI and an implementation proposal applied to nuclear research reactors is presented in this work, as well as its application to a TRIGA reactor using computer codes developed by ReliaSoft® Corporation.

Downloads

Download data is not yet available.

References

SOARES, W. A.; VASCONCELOS, V.; RABELLO, E. G. Risk-Based Inspection in the Context of Nuclear Power Plants, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2015, São Paulo. Annals… São Paulo: Comissão Nacional de Energia Nuclear, 2015.

MLADIN, D.; PRISECARU, I. Aspects of Probabilistic Safety Assessment for Triga Research Reactor. U.P.B. Sci. Bull., series C, v. 76, iss. 1, p. 261-270, 2014.

NASA - National Aeronautics and Space Administration. Probabilistic Risk Assessment Pro-cedures Guide for NASA Managers and Practitioners. NASA/SP-2011-3421, Second Edition, Hanover: NASA, 2011. 431 p.

IAEA - International Atomic Energy Agency. Basic Safety Principles for Nuclear Power Plants 75-INSAG-3 Rev. 1. INSAG 12, Vienna: IAEA, 1999. 105 p.

IAEA - International Atomic Energy Agency. Development and Application of Level 1 Prob-abilistic Safety Assessment for Nuclear Power Plants. Specific Safety Guide No. SSG-3, Vien-na: IAEA, 2010. 215 p.

IAEA - International Atomic Energy Agency. Application of Probabilistic Safety Assessment to Research Reactors. IAEA-TECDOC-517, Vienna: IAEA, 1989. 89 p.

CNEN - Comissão Nacional de Energia Nuclear. Inspeção em Serviço em Usinas Nucleoelé-tricas. CNEN NE 1.25, Rio de Janeiro: CNEN, 1996. 8 p.

EC - European Commission. Report on the Regulatory Experience of Risk-Informed In-service Inspection of Nuclear Power Plant Components and Common Views. EUR 21320 EN, Luxembourg: EC, 2004. 90 p.

IAEA - International Atomic Energy Agency. Application of Non-Destructive Testing and In-Service Inspection to Research Reactors. IAEA-TECDOC-1263, Vienna: IAEA, 2001. 52 p.

IAEA - International Atomic Energy Agency. Maintenance, Periodic Testing and Inspection of Research Reactors. IAEA Safety Guide No. NS-G-4.2, Vienna: IAEA, 2006. 81 p.

GA - General Atomic. Safeguards Summary Report for the New York University TRIGA MARK I Reactor. GA-9864, San Diego: GE, 1970. 150 p.

IAEA - International Atomic Energy Agency. Examples of In-Service Inspections and a Typical Maintenance Schedule for a Low-Power Research Reactor. Vienna. 2005. Available at: <https://ansn.iaea.org/Common/documents/Training/TRIGA%20Reactors%20(Safety%20and%20Technology)/pdf/chapter4.pdf>. Last accessed: 06 Nov. 2017.

Downloads

Published

2021-02-13

How to Cite

Marques, R. O., Vasconcelos, V., Soares, W. A., Silva Júnior, S. F., Raso, A. L., & Mesquita, A. Z. (2021). Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal. Brazilian Journal of Radiation Sciences, 8(3B (Suppl.). https://doi.org/10.15392/bjrs.v8i3B.371

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

Most read articles by the same author(s)

1 2 > >>