On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding
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2020
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Annals of Nuclear Energy
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After Fukushima Daiichi accident, the replacement of zirconium-based fuel cladding in Light Water
Reactors (LWR) became one of the main challenges of the nuclear industry. Austenitic steel–clad presents
some safety advantages comparing to zirconium alloys, noticeably, higher activation energy and lower
enthalpy of metal-water reaction. Thus, it produces a slower hydrogen release into the containment following
a postulated accident. In this study, a Loss-of-Coolant Accident (LOCA) aggravated by the complete
failure of the Emergency Core Cooling System (ECCS) is analyzed for a Small Modular Reactor
(SMR). Post-accident injection of inert gas into the containment is used as one of the hydrogen control
systems, to enhance safety margins during Severe Accidents (SA). The inertization system is successful
in complementing Passive Autocatalytic Recombiners (PAR) to perform combustible gas control.
Como referenciar
AVELAR, ALAN M.; MOURAO, MARCELO B.; MATURANA, MARCOS; GIOVEDI, CLAUDIA; ABE, ALFREDO Y.; PEDRASSANI, RAFAELA; SU, JIAN. On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding. Annals of Nuclear Energy, v. 149, p. 1-8, 2020. DOI: 10.1016/j.anucene.2020.107775. Disponível em: http://200.136.52.105/handle/123456789/31589. Acesso em: 19 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.