Analysis of containment pressure control strategy in HPR1000 NPP under severe accidents

Pingting Jiang , Yunna An , Wenxi Tian , Peng Chen , Dongyu He , Pingwen Ou , Deyang Xu
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Abstract

Containment is the last barrier of preventing the release of radioactive fission products in a nuclear power plant (NPP). It has the top priority of its strategy in a severe accident (SA) to ensure the integrity of containment. Generally, there are two ways for the containment heat removal. One is to set exchangers or sprays to cool the atmosphere in the containment like CPR1000. The other is to set sprays out of the steel containment to remove heat like AP1000. After Fukushima Daiichi nuclear accident, mitigation strategies after severe accidents are focused and specific systems of dealing with containment failure threat are required to design in new built NPPs. HPR1000 is a generation-Ⅲ PWR in China, which deployed the dedicated severe accident (SA) system of containment spray to address the above conditions. Containment spray in HPR1000 has two identical trains isolated physically, and each train is capable to reduce containment pressure after severe accidents. The containment spray system cannot start automatically, but only be started by operator during severe accidents. According to the lessons from Fukushima accident, it is hard for the operator to make the right choice in such a high-pressure environment during severe accidents, so the proper start-up time is better given in advance as possible. This paper assesses the effectiveness of the containment spray, conducts sensitive calculations of different start-up time, and discuss the negative effects of containment spray. Based on the calculation results, insights of containment spray strategy are gained for HPR1000 NPP and the proper start-up time for the strategy of containment spray in SAMG are put forward.

HPR1000核电厂严重事故下安全壳压力控制策略分析
安全壳是防止核电站放射性裂变产物释放的最后一道屏障。在严重事故(SA)中,其战略的首要任务是确保安全壳的完整性。通常情况下,安全壳排热有两种方式。一种是设置交换器或喷雾器,以冷却安全壳内的大气,如CPR1000。另一种是像AP1000一样,在钢制安全壳外设置喷淋,以去除热量。福岛第一核电站事故后,重点关注严重事故后的缓解策略,并要求在新建核电站中设计应对安全壳故障威胁的具体系统。华龙一号是我国第三代压水堆,为应对上述情况,我国部署了安全壳喷淋的严重事故专用系统。华龙一号中的安全壳喷淋有两个完全相同的列,它们在物理上被隔离,每个列都能够在发生严重事故后降低安全壳压力。安全壳喷淋系统不能自动启动,只能在严重事故时由操作员启动。根据福岛事故的教训,在严重事故中,操作员很难在如此高压的环境中做出正确的选择,因此最好提前给出合适的启动时间。本文评估了安全壳喷淋的有效性,对不同启动时间进行了敏感计算,并讨论了安全壳喷雾的负面影响。根据计算结果,深入了解了华龙一号核电站安全壳喷淋策略,并提出了SAMG安全壳喷淋战略的合适启动时间。
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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