池式反应堆剩余发热长期冷却分析  

The Analysis of Residual Heat Long Time Cooling about Pool-type Reactor

作　　者：王岩[1] 石琦[1] 陈晓明[1] 李金才[1] 周志伟[1] 

机构地区：[1]清华大学核能技术研究院,北京100084

出　　处：《核科学与工程》2002年第3期204-209,共6页Nuclear Science and Engineering

摘　　要：对一座池式反应堆剩余发热长期冷却进行了分析。剩余裂变功率通过求解中子动力学方程得出 ,剩余衰变功率采用我国最新的核工业标准EJ/T 745 92计算。传热计算采用一维传热模型。编制了计算程序 ,选取了合适的参数进行了计算并给出了与RETRAN 0 2程序计算结果的比较。最后还分析了剩余发热的冷却情况与池内水量、混凝土导热系数。The analysis of long term cooling for a pool type reactor after shutdown is presented. The heat from fission is obtained by solving the neutron kinetic equation. The heat from fission product decay is evaluated according to the Chinese National Standard EJ/T 745-92. For thermal analysis, 1 D lumped parameter heat conduction mode is used, and a computer code is programmed, the appropriate parameters are chosen to analyze the behavior of a pool type test reactor. The calculation results agree well with the results from RETRON-02 calculation. The relationship among the maximum pool water temperature, the water inventory and heat transfer coefficient has also been investigated.

关 键 词：池式反应堆 剩余发热 长期冷却 剩余裂变功率 中子动力学 停堆 堆芯 水池传热 剩余衰变功率 

分 类 号：TL32[核科学技术—核技术及应用]