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作 者:张盼[1] 刘宇生[1] 温丽晶[1] 胡文超[1] 许超
机构地区:[1]环境保护部核与辐射安全中心,北京100082
出 处:《核科学与工程》2017年第6期963-968,共6页Nuclear Science and Engineering
基 金:大型先进压水堆及高温气冷堆核电站国家科技重大专项"CAP1400核安全监管重要试验验证"(2015ZX06002007)
摘 要:试验验证是支撑新型先进压水堆核电技术的设计和核安全审评的重要手段,考虑到建设1∶1尺度的试验装置会导致高昂的建造成本,通常会开展比例试验研究。为了保证比例试验装置的重要现象与原型核电厂的现象具有相似性,试验获得的数据可以支撑原型电厂的设计,需要开展充分的比例分析工作。基于比例分析的重要性,文章以非能动核电厂AP1000的全厂断电事故为研究背景,采用H2TS方法开展了比例分析,重点关注了主回路自然循环阶段蒸汽发生器(SG)内的热工水力学行为,获得了相应的相似准则,并进行了失真分析,得出以下结论:当SG的高度比和流通面积比与系统级的高度比和流通面积比一致时,SG装置的关键现象与原型SG的关键现象之间存在相似关系;采用等物性模拟全厂断电事故情况下,蒸汽发生器换热能力远大于堆芯衰变功率,能够满足堆芯冷却的功能需求,蒸汽发生器换热量不存在失真。The test verification is an important means to support the new design and nuclear safety review of the advanced pressurized water reactor. It takes into account that the construction of an equal scale test facility would cost a lot of money, so the scaling test research was usually carried out. In order to ensure the similarity of important phenomena between the test facility and the prototype plant,and the test data can support the design of prototype plant, so it needs to carry out the detailed scalinganalysis for the test facility. Because of the importance of the scaling analysis,this paper is based on the background o~ station blackout accident in passive nuclear power plant, and it uses the H2TS method to carry out the scaling analysis. It focuses on the thermal-hydraulic behavior of steam generator during the main circuit natural circulation phase,and it obtains some similarity criteria and carries out the distortion analysis. The conclusions are as follows. When the height ratio and the flow area ratio of the SG are the same as the height ratio and the flow area ratio of the system level, the key phenomena o{ the SG device are similar to the prototype SG. If it uses the equal physical properties method to simulate the station blackout accident,the heat transfer capacity of the SG is much larger than the core decay power. So,the SG can meet the functional requirements of the core cooling, and its heat transfer capacity has no distortion.
分 类 号:TL332[核科学技术—核技术及应用]
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