Application of FMEA and FTA techniques for assessing the occurrence of LOCA in a TRIGA MARK I Reactor

Authors

DOI:

https://doi.org/10.15392/2319-0612.2024.2363

Keywords:

TRIGA IPR-RI, Loss of coolant accident, FMEA, FTA

Abstract

This study presents a framework merging failure mode and effect analysis (FMEA) and fault tree analysis (FTA) techniques to evaluate loss of coolant accident (LOCA) in the Brazilian Reactor TRIGA IPR-RI. At first, FMEA identified failure modes and prioritized risk management based on the risk priority number (RPN). Subsequently, FTA established logical relationships between these failure modes, revealing minimal cut sets. Results indicated that the path involving “loss of coolant from reactor tank” correlate to an externally caused leak, exhibiting a low probability and, consequently, a low RPN. On the other hand, the path involving “loss of coolant through primary circuit rupture without a pump shutdown” highlighted high RPN due to the lack of shutdown signals from the monitoring indicators. Finally, FTA unveiled that LOCA associates with a primary circuit rupture and the simultaneous failure of safety mechanisms, including ultimately human error.

Downloads

Download data is not yet available.

References

MENDES, C. Relatório do instituto de pesquisas radioativas. Escola de Engenharia, Universidade Federal de Minas Gerais, Belo Horizonte, Brazil. 1960.

IAEA - International Atomic Energy Agency. Safety of research reactors. IAEA Safety Standards Series No. SSR-3, Vienna: IAEA, 2016.

IAEA - International Atomic Energy Agency. Operational limits and conditions and operating procedures for research reactors. IAEA Safety Standards Series No. NS-G-4.4, Vienna: IAEA, 2008.

USNRC – United States Nuclear Regulatory Commission. Guidelines for preparing and reviewing applications for the licensing of non-power reactors. NUREH 1537, Washington: USNRC, 1996.

GA – General Atomics. Technical foundation of TRIGA. GA 471, San Diego: GA, 1958.

GA – General Atomics. TRIGA MARK I reactor – Mechanical maintenance and operating manual. GA 1544, San Diego: GA, 1960.

IAEA - International Atomic Energy Agency. EPR-research reactor – Attachment 1 - Generic procedures for response to a nuclear or radiological emergency at TRIGA research reactor. Emergency Preparedness and Response, Vienna: IAEA, 2011.

CDTN – Centro de Desenvolvimento da Tecnologia Nuclear. Relatório final de análise de segurança do reator TRIGA IPR-RI. RFAS/REATOR TRIGA IPR-RI/CDTN, Belo Horizonte: CDTN, 2022.

BOCK, H.; KIRCHSTEINGER, C. Probabilistic safety analysis for the reactor Vienna. (AIAU-88305), Vienna: AIAU, 1988.

YOUSEFPOUR, F.; KARIME, K.; SOLTAMI, H. Comparative reliability analysis for two different designs of residual heat removal system (RHRS) and containment spray system (CSS) of IR-360 nuclear power plant. In: INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, 2010, Portoroz. Annals… Portoroz: Nuclear Society of Slovenia, 2010. p. 410.

SOLOM, M.; CHANCE, C.; PANNIER, C.; SEAGER, R.; LEE, A.; GREEN, J.; DUONG, T.; ALICEA, P. Risk analysis of the residual heat removal system at south Texas project with a special focus on breach of containment. In: 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE, 2012, Anahein. Annals… Anahein: The American Society of Mechanical Engineers, 2012. p. 321-331. DOI: https://doi.org/10.1115/ICONE20-POWER2012-54200

GA – General Atomics. Safeguards summary report for the New York University TRIGA MARK I reactor. GA 9864, San Diego: GA, 1970.

MARQUES, A.R (2018). Inspeção Baseada Em Risco No Contexto De Reatores Nucleares: Estado Da Arte, Diretrizes E Procedimentos Para Sua Utilização (Master’s dissertation, Centro de Desenvolvimento da Tecnologia Nuclear).

RC - Reliasoft Coroporation. User’s guide XFMEA + version 2021. Reliasoft Corporation, Tucson, 2021.

RC - Reliasoft Coroporation. User’s guide BlockSim version 2021. Reliasoft Corporation, Tucson, 2021.

CAI, B.; LIU, Y.; ZHANG, Y.; FAN, Q.; LIU, Z.; TIAN, X. A dynamic Bayesian networks modeling of human factors on offshore blowouts. Journal of Loss Prevention in the Process Industries, v. 26, p. 639-649, 2013. DOI: https://doi.org/10.1016/j.jlp.2013.01.001

SENOL, Y. E.; SAHIN, B. A novel Real-Time Continuous Fuzzy Fault Tree Analysis (RC-FFTA) model for dynamic environment. Ocean Engineering, v. 127, p. 70-81, 2016. DOI: https://doi.org/10.1016/j.oceaneng.2016.09.035

PEETERS, J.F.W.; BASTEN, R.J.I.; TINGA, T. Improving failure analysis efficiency by combining FTA and FMEA in a recursive manner. Reliability Engineering & System Safety, v. 172, p. 36-44, 2018. DOI: https://doi.org/10.1016/j.ress.2017.11.024

CDTN – Centro de Desenvolvimento da Tecnologia Nuclear. Ensaio de inspeção visual em componentes estruturais e partes dos combustíveis do reator IPR-RI. NI – EC2-001/06, Belo Horizonte: CDTN, 2006.

ALENCAR, D. A.; SILVA, S. F. Acompanhamento do Ensaio de Inspeção Visual nos Combustíveis do Reator IPR-R1. NI/RD-AT1-004/00/CDTN, Belo Horizonte: CDTN, 2000.

BERROCAL. Determinação do Nível de Vibrações Sísmicas do Terreno Provocadas pelo Sismo Básico de Projeto no Centro de Desenvolvimento da Tecnologia Nuclear, em Belo Horizonte, MG. São Paulo: IAG/USP. 2006.

HASSAN, A.; MASKIN, M.; PRAK TOM, P.; BRAYON, F.; HLAVAC, P.; MOHAMED, F. Operator response modeling and human error probability in TRIGA Mark II research reactor probabilistic safety assessment. Annals of Nuclear Energy, v. 102, p. 179-189, 2017. DOI: https://doi.org/10.1016/j.anucene.2016.12.024

MASKIN, M.; HASSAN, A.; BRAYON, F.C.; PHONGSAKORN, P.T.; ZAKARIA, M.F.; RAMLI, Z.; MOHAMED, F. Quantification of initiating event frequencies and component reliability data in level 1 probabilistic safety assessment at Puspati TRIGA research reactor. Annals of Nuclear Energy, v. 121, p. 22-28, 2018. DOI: https://doi.org/10.1016/j.anucene.2018.07.013

USNRC – United States Nuclear Regulatory Commission. Common-Cause Failure Database and Analysis Sistem: Event Data Collection, Classification and Coding. NUREG/CR-6268, Washington: USNRC, 2007.

Downloads

Published

2024-01-17

Issue

Section

Articles

How to Cite

Application of FMEA and FTA techniques for assessing the occurrence of LOCA in a TRIGA MARK I Reactor. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 12, n. 1, p. e2363, 2024. DOI: 10.15392/2319-0612.2024.2363. Disponível em: https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/2363.. Acesso em: 27 apr. 2024.

Similar Articles

1-10 of 819

You may also start an advanced similarity search for this article.

Most read articles by the same author(s)