Application of FMEA and FTA techniques for assessing the occurrence of LOCA in a TRIGA MARK I Reactor
DOI:
https://doi.org/10.15392/2319-0612.2024.2363Keywords:
TRIGA IPR-RI, Loss of coolant accident, FMEA, FTAAbstract
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.
- Views: 126
- PDF Downloads: 95
- XML Downloads: 10
Downloads
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.
Published
How to Cite
Issue
Section
License
Copyright (c) 2024 Brazilian Journal of Radiation Sciences
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/
