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本课题来源于创新型核反应堆与燃料循环国际计划(INPRO)中的IND5合作项目——液态金属冷反应堆安全级余热排出系统整体模拟。研究内容是以印度原型快堆PFBR的安全级余热排出系统设计(SGDHRs)作为标准例题,对其进行整体模拟。采用快堆系统安全分析程序OASIS3.2进行了整体模拟。稳态计算结果(表1)显示,在热备用工况下,事故余热中间回路及空气侧均可实现自然循环流动。以失去厂外电作为初因事件进行了瞬态分析,计算结果显示,在紧急停堆后失去正常排热途径的情况下,SGDHRs可以有效地排出堆芯衰变热。
This topic derives from the IND5 cooperation project in INPRO - the overall simulation of the waste heat rejection system for liquid metal cooled reactors. The content of this study is based on the standard example of safety-level waste heat removal system design (SGDHRs) of PFBR in India. Using fast reactor system safety analysis program OASIS3.2 overall simulation. The steady-state results (Table 1) show that in the hot standby condition, the natural circulation flow can be achieved both in the intermediate circuit of the accidental heat and in the air side. A transient analysis of the loss of off-site electricity as a primary event was carried out. The calculation results show that SGDHRs can effectively dissipate the decay heat of the core under the condition of losing normal heat release after emergency shutdown.