Abstract 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.

中文翻译：

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后惰化不锈钢包壳小型模块化反应堆提高核安全性

摘要 福岛第一核电站事故后，轻水堆（LWR）中锆基燃料包壳的替代成为核工业面临的主要挑战之一。与锆合金相比，奥氏体钢包层具有一些安全优势，明显的是，更高的活化能和更低的金属-水反应焓。因此，在假定的事故发生后，它会产生较慢的氢气释放到安全壳中。在本研究中，针对小型模块化反应堆 (SMR) 分析了因紧急堆芯冷却系统 (ECCS) 完全故障而加剧的冷却剂损失事故 (LOCA)。事故后将惰性气体注入安全壳用作氢气控制系统之一，以提高严重事故 (SA) 期间的安全裕度。