快堆燃料组件的子通道分析

SUBCHANNEL ANALYSIS OF FUEL ASSEMBLY FOR FAST REACTOR

开发了THAS-PC2子通道分析微机程序,用于计算稳态和瞬态工况下快堆燃料组件的流量、温度和压力等参量分布。对EFR燃料组件的稳态和瞬态计算结果如下:堆芯出口平均温度和温升分别为557℃和157℃,最高包壳表面温度为601℃,它发生在中心燃料棒上,最大冷却剂温度为593℃;主泵断电二次停堆事故作为瞬态计算,算得的最高冷却剂温度和最高包壳表面温度分别为630℃和637℃(当t=2s时),它们都远低于钠沸腾温度和设计限制值,证明在这种事故中快堆是安全的。

A subchannel analysis code THAS--PC2 running on a microcomputer is developed to computethe flow, temperature and pressure distributions in fast reactor fuel assembly for both steady stateand transient conditions. The steady state and transient calculations of the fuel assembly for the Experimental Fast Re-actor are made on a microcomputer by use of THAS--PC2 code. The calculated results for thesteady state are as follows: average core exit temperature and temperature rise are 557℃ and157℃ respectively, maximum cladding surface temperature and maximum fuel center temperatureare 601℃ and 2410℃ respectively, which occur all on the central fuel pin. The maximum coolanttemperature is 593℃. The loss of primary pump power accident (secondary scram) is chosen forthe transient calculation. The calculated maximum coolant temperature and maximum claddingsurface temperature are 630℃ and 637℃ respectively when t = 2s. They are far lower than boil-ing point of sodium and safety limit value.