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机构地区:[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041
出 处:《核动力工程》2014年第1期152-155,共4页Nuclear Power Engineering
摘 要:针对初步设计的非能动余热排出系统方案并结合模块化反应堆的结构和运行特点,对非能动余热排出系统进行合理的控制体和节点划分并建立数学物理模型,采用数值迭代方法和通用热工水力分析程序,分析非能动余热排出系统的瞬态热工水力特性。结果表明,反应堆发生断电事故后,系统自然循环可以很快建立;在非能动余热排出过程中,换热器中二次侧始终为液相,没有发生流动不稳定;应急冷却器换热面积在一定范围内变化对系统余热排出能力没有显著影响。Based on the preliminary design passive residual heat removal system project of the modular reactor, and considering the structure and operation characteristics, the reasonable control volumes are divided and the mathematical models are established. Using numerical iteration method and in common currency program, the transient.state codes is adopted to analyze the thermo-hydraulic characteristics of the passive residual heat removal system. The results show that, after the reactor power failure, natural circulation of system can quickly be established; in the passive residual heat removal process, no flow instability happens; emergency cooler heat exchange area change of residual heat removal capability has no significant effect in a certain range.
分 类 号:TL331[核科学技术—核技术及应用]
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