Study on the Simulation of Heat Generation in Nuclear Core for Small Power Reactor

摘要：

Research on small sized light water reactors is one of the focuses in the field of nuclear reactor. There are various utilizations of small sized reactors such as electricity generation, sea water desalination, etc. The thermal-hydraulic experiment research is an indispensable process in technology innovating. The study on the simulation of heat generation in nuclear core has been done, as a very important part of thermal-hydraulic experiment research on the small power reactor. In the experiment, electric heating pipes generate heat and beget resistance to simulate the PWR fuel rods. The heat is generated by electrifying through stainless steel pipes. Design of the heating pipes is present in this paper. Numerical simulations of the electric heating pipes on electromagnetism, mechanics and hydraulics have been done, A guide of current limitation is give for preventing the pipes tangent and then shorted, which happened in early test. Experimentations have been done on improved heating pipes. The pipes are up to the design standard and safe enough, which are proved by results of calculations and experimentations.

关键词： Mural-direct-heating High-power Electric Heating Module Simulation of the Core of Nuclear Reactor

作者: Guo Qiang Jia Haijun Yin Huaqiang Zou Guisheng

作者单位: Institute of Nuclear & New Energy Technology, Tsinghua University, Beijing 100084, China Department of Mechanical Engineering, Tsinghua University, Beijing 100084, China

会议类型: 国际会议

会议名称: ISSNP2008、CSEPC、ISOFIC2008(第二届21世纪和谐核电系统国际会议、第四届电厂控制中认知系统工程方法国际会议暨第三届未来核电厂仪表与控制国际会议)

会议地点: 哈尔滨

会议语种:英文

页码: 256-260

在线出版日期: 2008-09-08（万方平台首次上网日期，不代表论文的发表时间）