池式快堆堆本体中液体晃动效应的研究进展

Research progress of liquid sloshing in the reactor vessel of pool-type fast reactor

堆本体是核反应堆的核心组件,也是核反应堆进行核聚变或核裂变反应的关键部位。池式快堆堆本体内部的液态金属冷却具有大自由液面特征,其内部液体出现晃动可能会对核反应堆的安全性和稳定性造成不利影响,因此开展池式快堆堆本体中液体晃动效应的研究具有重要意义。首先,阐述了液体的晃动效应,并介绍了池式快堆堆本体的结构形式;其次,从理论研究、数值模拟和振动台试验三个方面对池式快堆堆本体的液体晃动研究进行了讨论分析。研究结果表明:单一的理论方法、数值模拟或振动台试验难以准确捕捉液体晃动对堆本体结构的实际影响,结合使用这三种方法能够获得更为准确和全面的研究效果;最后,对既有研究进行了梳理与总结,以期为池式快堆堆本体的进一步抗震研究提供新的思路和启发。

The reactor vessel is the core component of a nuclear reactor and is also the key part for nuclear fusion or fission reactions.The liquid metal coolant inside the pool-type fast reactor vessel has a large free liquid surface,and any liquid motion inside may have adverse effects on the safety and stability of the nuclear reactor.Therefore,it is of great significance to study the sloshing effect of liquid in the tank fast reactor vessel.Firstly,the sloshing effect of the liquid is described,and the structural form of the pool-type fast reactor core is introduced.Secondly,the study of liquid motion in the pool-type fast reactor vessel is discussed and analyzed from three aspects:theoretical research,numerical simulation,and shaking table experiments.The results show that it is difficult to accurately capture the actual impact of liquid motion on the reactor vessel structure using a single theoretical method,numerical simulation,or shaking table experiment.The combined use of these three methods can provide more accurate and comprehensive research results.Finally,existing research is reviewed and summarized,aiming to provide new ideas and inspiration for further seismic research on pool-type fast reactor vessel.