Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1
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2011
Autores IPEN
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 10th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 17th; MEETING ON NUCLEAR INDUSTRY, 2nd
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HIRATA, DANIEL M.; SABUNDJIAN, GAIANE. Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 10th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 17th; MEETING ON NUCLEAR INDUSTRY, 2nd, October 24-28, 2011, Belo Horizonte, MG. Proceedings... Disponível em: http://repositorio.ipen.br/handle/123456789/16245. Acesso em: 26 Apr 2024.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.
Assuntos
damage; depressurization systems; deterministic estimation; fault tree analysis; flow blockage; iear-1 reactor; loss of coolant; loss of flow; nuclear damage; pipes; primary coolant circuits; probabilistic estimation; reactor operation; reactor shutdown; risk assessment; safety analysis; safety injection; eccs