Status of Investigation to Ensure Applicability of ECCS Acceptance Criteria to High-Burnup Fuel

Q4 Engineering
M. Ozawa, M. Amaya
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引用次数: 0

Abstract

Light-water reactors (LWRs) are equipped with an emergency core cooling system (ECCS) that is designed to maintain the coolable geometry of the reactor core and finally minimize the release of radioactive fission products to the public and environment even in a loss-of-coolant accident (LOCA). Acceptance criteria for the ECCS of LWRs were determined to evaluate the safety function and performance in the design and to ensure a sufficient safety margin in the results of the evaluation. The latest revision of the criteria was made in 1981 in Japan, referring to the additional knowledge obtained after the previous revision. Fuel burnup has been extended by changing cladding materials, fuel design, etc., since the latest revision. Correspondingly, knowledge has been accumulated through studies on high-burnup fuel behavior under LOCA conditions to confirm the safety during the LOCA. This paper is a summary of the investigation and remaining issues on the applicability of the current Japanese ECCS acceptance criteria to high-burnup fuel, considering the history and basis of the current acceptance criteria. Results of the investigation conducted up to now reveal that the influence of burnup extension is small in terms of the cladding behavior of high-temperature oxidation and the fracture limit in quenching during the LOCA condition, and the current criteria are applicable even in the case of high-burnup fuel.
确保ECCS验收标准适用于高燃耗燃料的研究现状
轻水反应堆(LWRs)配备了应急堆芯冷却系统(ECCS),该系统旨在保持反应堆堆芯的可冷却几何形状,并最终最大限度地减少放射性裂变产物向公众和环境的释放,即使在冷却剂损失事故(LOCA)中。确定了轻水堆ECCS的验收标准,以评估设计中的安全功能和性能,并确保评估结果有足够的安全裕度。该标准的最新修订于1981年在日本进行,参考了上次修订后获得的额外知识。自最新版本以来,通过改变包层材料、燃料设计等,燃油燃耗得到了延长。相应的,通过对LOCA条件下高燃耗燃料行为的研究积累了知识,证实了LOCA过程中的安全性。本文结合日本现行ECCS验收标准的历史和依据,总结了日本现行ECCS验收标准对高燃耗燃料适用性的调查和遗留问题。迄今为止的研究结果表明,燃耗延长对高温氧化包层行为和LOCA状态下淬火断裂极限的影响很小,即使在高燃耗燃料的情况下,现行准则也适用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Transactions of the Atomic Energy Society of Japan
Transactions of the Atomic Energy Society of Japan Energy-Nuclear Energy and Engineering
CiteScore
0.50
自引率
0.00%
发文量
16
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