Investigation on Transient Thermohydraulics of a Plate Type Research Reactor
A thermohydraulic and safety analysis code has been developed with Fortran90 language to investigate the transient thermohydraulic characteristics of a plate-like fuel research reactor. For the development of this code, a series of corresponding mathematical and physical models were applied. All possible flow and heat transfer conditions during the transient were considered and the optional correlations were supplied. The usual finite difference method was abandoned and the integral technique was adopted to evaluate the temperature field of the plate type fuel elements. The reactor under research was composed of two kinds of assemblies:standard fuel assemblies (SFA) and control fuel assemblies (CFA). In order to simulate the loss of flow accident (LOFA), which was an anticipated accident of a research reactor, each fuel assembly in the whole core was modeled and simulated. The evolvement of the mass flux distribution was given out, and the variation of the temperature of fuel elements and coolant was also investigated. Furthermore, a whole SFA assembly was modeled to analysis the blockage of a channel in this assembly, which may happen during the lifetime of the reactor due to the fuel swelling. Results of coolant flow and temperature distribution under this condition were given out.
Plate type reactor Transient thermo-hydraulics Research reactor Loss of flow accident
Lu Qing Qiu Sui zheng Tian Wenxi Su Guanghui
Department of nuclear science and technology, Xian Jiaotong University, Shanxi, China
国际会议
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)
哈尔滨
英文
186-192
2008-09-08（万方平台首次上网日期，不代表论文的发表时间）