MODELING LOFW IN A PWR USING MELCOR
DOI:
https://doi.org/10.15392/bjrs.v8i3A.1355Palavras-chave:
severe accident, MELCOR, PSA.Resumo
The Probabilistic Safety Assessment (PSA) is part of a Nuclear Power Plant (NPP) licensing process. It considers the elaboration and updating of probabilistic models that estimate the risk associated to the operation, allowing the risk monitoring from the design to the plant decommissioning, for both operational as regulatory activities. The PSA identifies those components or plant systems whose unavailability contributes significantly to the Core Damage Frequency (CDF) and to the Large Early Release Frequency (LERF) of radioactive material. Based on the PSA Level 1 results for a reference plant under design, the Analysis, Evaluating and Risk Management Laboratory (LabRisco), located in the University of São Paulo (USP), Brazil, started the analytical investigation of severe accident phenomena using the US Nuclear Regulatory Commission (NRC) MELCOR2.2 code – focusing on the qualification of a group of specialists who will subsidize a PSA Level 2 for the same plant. This PSA Level 1 shows that the accident with large CDF contribution is the Loss of Feed Water Accident (LOFW). Therefore, the initial objective of the investigation was to model the progression of severe accidents during a LOFW for the reference Pressurized Water Reactor (PWR) and to analyze the response of the plant under these accident scenarios. During the course of the hypothetical LOFW in the reference plant, hydrogen was generated – by a reaction between the high temperature steam water and the fuel-cladding inside the reactor pressure vessel (RPV) but not representing a serious threat to the RPV integrity.
Downloads
Referências
U.S. Nuclear Regulatory Commission –USNRC. Probabilistic Risk Assessment and Severe accident Evaluation for New Reactors, NUREG-0800, Section 19.0, Washington, D. C., (2007).
M. R. Hayns. The Evolution of Probabilistic Risk Assessment in the Nuclear Industry, Institution of Chemical Engineers, Trans I, v. 77, Part B, (1999).
M. R. Martins, P. F. F. Melo and M. C. Maturana. Methodology for system reliabilityanalysis during the conceptual phase of complex system design considering humanfactors”. In: Proceeding of the ANS PSA 2015 International Topical Meeting onProbabilistic Safety Assessment and Analysis, Sun Valley, ID, April 26-30, 2015, onCD-ROM, American Nuclear Society, LaGrange Park, IL, (2015).
M. C. Maturana, L. L. Bruno, and M. R. Martins, Application of Fire PSA inDefining System Reliability Criteria: Detection and Suppression Systems in I&CElectrical Panel Room, In: Proceedings of Probabilistic Safety Assessment andManagement – PSAM 14, Los Angeles, CA, September, (2018).
L.L. Humphries, et al. MELCOR Computer Code Manuals Vol. 1: Primer andUsers’ Guide Version 2.2.9541 (2017).
L.L. Humphries, et al. MELCOR Computer Code Manuals Vol. 2: Primer andUsers’ Guide Version 2.2.9541 (2017).
N. N. Araújo, M. C. Maturana, M. R. Gual, Analytical Simulation of a PWR UsingMELCOR Code, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, ,Santos, SP, Brazil, October 21-25 (2019).
J. Cardoni, R. Gauntt, D. Kalinich and J. Phillips, MELCOR simulations of severeaccident at Fukushima Daiichi Unit 3, Nuclear Technology, 2, Volume 186 (2014).
T. Sevon, A MELCOR model of Fukushima Daiichi Unit 3 accident, NuclearEngineering and Design, 284, pp. 80-90, April (2015).
M. Genta Maragni, A. Belchior Junior and J. A. Onoda Pessanha. Modelagem eestado estacionário do reator da INAP com o RELAP5/MOD2, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, (1997).
M. Malcki, L. Pienkowski, K. Skolik, Simulation of SB-LOCA of typical PWR withMELCOR code, In: IOP Conference Series Earth and Environmental Science,214:012071, January (2019).
M Pescarini, F. Mascari, D. Mostacci and F De Rosa, Analysis of unmitigated largebreak loss of coolant accidents using MELCOR code, Journal of Physics ConferenceSeries 923, Volume 1,012009, November (2017).
Y. Jin, W. Xu, X. Liu, In- and ex-vessel coupled analysis of IVR-ERVCphenomenon for large scale PWR, Annals of Nuclear Energy, Volume 80, pp. 322-337, June (2015).
M. Pavlova, P. P Groudev and V. Hadjiev, Development and validation of VVER-1000 input deck for severe accident calculations with MELCOR Computer Code, In: XVInternational School on Nuclear Physics, Neutron Physics and NuclearEnergy, Varna, Bulgaria, October (2003).
NUREG‐0800: Standard Review Plan for the Review of Safety Reposts for NuclearPower Plants: LWR Edition, Revision 2, June (2007).
USNRC Regulations Title 10, Code of Federal Regulations (CRF), Part 50 - DomesticLicensing of Production and Utilization Facilities, Section 50.44 Combustible gascontrol for nuclear power reactors, January 1( 2011).
Y. Abou-Rjeily, G. Cénérino, A. Drozd, S. Lee, J. Misak, C.O. Park, et al.International Atomic Energy Agency, Mitigation of Hydrogen Hazards in SevereAccident in Nuclear Power Plants, IAEA-TECDOC-1661 (2011).
J. Yanez J, M. Kuznetso, A. Souto‐Iglesias A. An analysis of the hydrogen explosionin the Fukushima‐Daiichi accident, Int J Hydrogen Energy, Volume 40, pp. 8261‐8280 (2015).
AptPlot 6.8.0 / ACS Plug-in 2.3.0 - released December 1 (2017).
Downloads
Publicado
Edição
Seção
Licença
Direitos autorais (c) 2021 Brazilian Journal of Radiation Sciences
Este trabalho está licenciado sob uma licença Creative Commons Attribution 4.0 International License.
Declaro que o presente artigo é original, não tendo sido submetido à publicação em qualquer outro periódico nacional ou internacional, quer seja em parte ou em sua totalidade. Declaro, ainda, que uma vez publicado na revista Brazilian Journal of Radiation Sciences, editada pela Sociedade Brasileira de Proteção Radiológica, o mesmo jamais será submetido por mim ou por qualquer um dos demais co-autores a qualquer outro periódico. Através deste instrumento, em meu nome e em nome dos demais co-autores, porventura existentes, cedo os direitos autorais do referido artigo à Sociedade Brasileira de Proteção Radiológica, que está autorizada a publicá-lo em meio impresso, digital, ou outro existente, sem retribuição financeira para os autores.
Licença
Os artigos do BJRS são licenciados sob uma Creative Commons Atribuição 4.0 Licença Internacional, que permite o uso, compartilhamento, adaptação, distribuição e reprodução em qualquer meio ou formato, desde que você dê o devido crédito ao (s) autor (es) original (is) e à fonte, forneça um link para a licença Creative Commons, e indique se mudanças foram feitas. As imagens ou outro material de terceiros neste artigo estão incluídos na licença Creative Commons do artigo, a menos que indicado de outra forma em uma linha de crédito para o material. Se o material não estiver incluído no licença Creative Commons do artigo e seu uso pretendido não é permitido por regulamentação legal ou excede o uso permitido, você precisará obter permissão diretamente do detentor dos direitos autorais. Para visualizar uma cópia desta licença, visite http://creativecommons.org/licenses/by/4.0/
