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超临界水堆与先进沸水堆安全特性差异性分析

Comparative Safety Analysis between SCWR and ABWR
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摘要 超临界水堆和先进沸水堆在结构和原理上存在很多相似点,但在安全特性方面存在一定的差异性。本文通过对比分析超临界水堆和先进沸水堆两个堆型来研究它们安全特性的差异性,研究结果表明:超临界水堆由于不存在汽水两相,不会发生偏离泡核沸腾现象,又因为采用的是非能动和能动相结合系统,具有较好的安全特性;和相同功率的先进沸水堆相比,其比焓高,流量低,泵消耗功率低,压力下降速率更快,消耗的核燃料低;超临界水堆安全系统与先进沸水堆安全系统虽然都采用了非能动安全系统和能动系统,但在超临界水堆能动安全系统中,其压力控制系统控制速度较快,而非能动控制系统则较为稳定。 There are many similarities in structure and principle between Supercritical water reactor(SCWR) and advanced boiling water reactor(ABWR).However,There are some different safety characteristics in them.Compared with both analysis of SCWR and ABWR reactor core and safety systems,we concluded that SCWR water is no phase change and the core without burning phenomenon behind supercritical pressure.SCWR ABWR safety system and safety systems are non- safe systems and passive systems,but SCWR passive safety systems,which control the pressure control system faster,rather than the active control system is more stable.Therefore,SCWR on the security features of safety coefficient is better than ABWR.
出处 《核安全》 2016年第4期59-64,共6页 Nuclear Safety
基金 中核核反应堆系统设计技术重点实验室课题 项目编号2014BH0041 中央高校基本科研业务专项资金项目 项目编号2014BJ0086
关键词 超临界水堆 先进沸水堆 堆芯系统 安全系统 安全特性 SCWR ABWR Core system Security System Security Features
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