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STUDY ON TYPICAL INITIAL EVENT OF ATWS FOR SMALL MODULAR REACTOR

机译:小型模块化反应器ATWS典型初始事件的研究

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The method for ATWS (anticipated transient without scram) analysis was completely developed for commercial pressurized water (PWR) reactor plants, especially for selecting of typical initial events. For accident analysis of ATWS, it is different between PWR and small modular reactor (SMR), as different structures and characters, and it is necessary to study the typical initial events for these reactors. Based on the standard of PWR, the demanding for ATWS analysis was studied and the consequences for typical anticipated transient was calculated using RELAP5/MOD3.2 code, "maintain reactor coolant pressure boundary integrity" was selected as limiting criterion. The results shows for SMR, anticipated transient with the most serious consequence for ATWS are loss of offsite power and inadvertent control rod withdraw event, this conclusion will support to prepare the safety analysis report and optimum design of diversity activation system (DAS) for SMR.
机译:完全针对商业压水(PWR)反应堆工厂开发了ATWS(预期的无扰动瞬态)分析方法,尤其是用于选择典型的初始事件。对于ATWS的事故分析,压水堆和小型模块化反应堆(SMR)之间存在差异,因为结构和特征不同,因此有必要研究这些反应堆的典型初始事件。基于压水堆的标准,研究了对ATWS分析的要求,并使用RELAP5 / MOD3.2代码计算了典型预期瞬态的后果,选择了“维持反应堆冷却剂压力边界完整性”作为限制标准。结果表明,对于SMR,预期的瞬变对ATWS造成的最严重后果是场外功率损失和意外的控制杆撤回事件,该结论将有助于编写SMR的安全性分析报告和分集激活系统(DAS)的最佳设计。

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