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首页> 外文期刊>Annals of nuclear energy >SBLOCA long term cooling procedure for the integral type PWR
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SBLOCA long term cooling procedure for the integral type PWR

机译：SBLOCA一体式PWR的长期冷却程序

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An advanced integral-type pressurized water reactor (IPWR) with a maximum thermal power of 65 MW has been developed at the Korea Atomic Energy Research Institute (KAERI). This 65 MW IPWR enhances the safety and reliability by adopting inherent safety design characteristics and an advanced passive design feature. To identify the transient behavior and coolant distribution in the reactor coolant system (RCS) during a small break loss of coolant accident (SBLOCA), the break size spectrum analyses for the limiting break location are performed using a best-estimate code of MARS/ SMR. The analysis results show that the safety systems of the 65 MW IPWR design adequately remove the core decay heat without causing a core uncovery for all the break cases. However, for some of the relatively large sizes of the breaks, the upstream region of the shutdown cooling system (SCS) suction pipe is completely voided after the break and it is not refilled with safety injection water throughout the transient, which prevents a proper operation of the normal SCS. Based on the results of this analysis, the 65 MW IPWR specific long term cooling (LTC) procedure, independent of a break size, is suggested instead of using the normal operation of the SCS.
机译：韩国原子能研究所（KAERI）已经开发出一种先进的整体式压水堆（IPWR），其最大热功率为65兆瓦。这款65 MW IPWR通过采用固有的安全设计特性和先进的无源设计功能，提高了安全性和可靠性。为了确定在少量冷却剂事故损失（SBLOCA）期间反应堆冷却剂系统（RCS）中的瞬态行为和冷却剂分布，使用MARS / SMR的最佳估计代码对极限中断位置进行了中断尺寸谱分析。分析结果表明，65 MW IPWR设计的安全系统可充分消除堆芯衰减热，而不会导致所有断裂情况下的堆芯揭露。但是，对于某些较大的中断，在中断之后，停机冷却系统（SCS）吸入管的上游区域会完全排空，并且在整个瞬态过程中都不会重新注入安全注入水，这会阻止正常运行普通SCS。根据此分析的结果，建议使用65 MW IPWR特定于长期冷却（LTC）的程序，而与中断大小无关，而不是使用SCS的正常操作。

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