驳船-堆耦合条件下海上核电站扩展极限响应措施

Jue Wang, Longze Li, Chen Hu, W. Cong
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引用次数: 0

摘要

与陆基核电站相比,海上核电站的运行条件要复杂得多。例如,在工厂安全分析中,应考虑与自然事件和人为事件同等重要的驳船平台故障。因此,在制定相应的电厂运行程序时,应考虑与驳船和反应堆状态耦合的二维运行状态。另一方面,ONPP的独特和非预期的外部事件的结合所导致的超出设计基础的危害可能导致传统和二维程序的盲区。由于现有运行条件和相关程序不足以应对上述事件,因此制定了扩展运行策略,即超出设计基础危害和扩展极限响应措施,在一次系统降压后直接向反应堆压力容器注入海水,必要时对安全壳进行排气,形成了极限响应措施的基础;这是台湾电力公司在福岛事故后提出的。考虑到海上和驳船的特点,最终响应措施可以扩展为包括通过二次侧被动余热排除管线间接向蒸汽发生器注入海水和通过Kingston阀向反应堆舱室注水,以重建一个新的分层反应堆。最后,利用热液集成计算机代码对主要面向电站指挥人员和操作人员的扩展极限响应措施进行了初步分析,验证了系统配置和运行策略的有效性。结果表明,向蒸汽发生器注入海水可以有效地去除衰变热,并且敏感性研究表明操作员干预对事故的缓解效果较好。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions
Compared with the land-based nuclear power plant, the operating conditions of offshore nuclear power plant (ONPP) are much more complicated. For example, the barge-mounted platform malfunction, which is as important as the natural events and human events, should be considered in the plant safety analysis,. As a result, a two dimension operating condition coupled with barge and reactor status should be considered in the development of relevant power plant operating procedures. On the other hand, the beyond design basis hazards induced by the combination of unique and unanticipated external events of ONPP may lead to a blind area to both traditional and two dimension procedures mentioned above. Due to the insufficiency of existing operating condition and relevant procedures to tackle with the above events mentioned, an expanded operation strategy, namely the beyond design basis hazards and the extended ultimate response measures, is developed, Injecting sea water into reactor pressure vessel directly after primary system depressurized and venting the containment when necessary, formed the basis of ultimate response measure, which was proposed by Taiwan Power Company after Fukushima Accident. Considering the offshore and barge-mounted features, the ultimate response measure can be extended to include sea water injection into steam generator indirectly through secondary side passive residual heat removal lines and reactor cabin flooding by sea water through Kingston valves, to rebuild a newly, hierarchical one. Finally, the extended ultimate response measures, provided mainly for the plant command staff and operators, are analyzed utilizing thermal-hydraulic integral computer code preliminarily, to prove the effectiveness of the system configuration and operating strategy. It is concluded that injecting sea water into steam generator can remove the decay heat effectively, and the sensitivity study shows that operator intervention is good enough in accident mitigation.
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