【摘要】 核能作为清洁能源,逐渐替代煤炭做为冬季供热的热源,池式常压低温供热堆具有良好的固有安全性,是最可行的方案之一。针对池式常压低温的堆芯结构、组件形式以及反应堆总体运行参数,使用子通道分析程序COBRA进行计算分析,对程序中的部分传热模型和CHF模型进行了修改,使之适用于低温常压状态运行的反应堆热工水力设计计算。使用改进的子通道分析程序COBRA计算分析了反应堆整个寿期内最危险时刻的反应堆热工水力参数,验证了堆芯稳态热工的安全性。通过对计算结果的分析表明,整个寿期内,堆芯稳态最小烧毁比(MDNBR)为3.485,燃料棒包壳表面最高温度为187℃,芯块中心最高温度为1 902℃,堆芯热工能够满足反应堆安全要求,并为反应堆的事故工况留有足够的安全裕量。更多还原

【Abstract】 As a clean energy,the nuclear energy has been increasingly considered as an alternative to coal for heating in winter.The pool type normal pressure low temperature heating reactor is one of the most applicable solutions due to its good inherent safety features.According to the reactor core structure,fuel assembly structure,and general operating parameters,the sub channel code COBRA was used to perform the thermal hydraulic calculation and analysis.Some heat transfer models and CHF models in COBRA code were modified to make it suitable to the thermal hydraulic design and calculation of the reactor at low temperature and normal pressure.The modified sub channel analysis code COBRA was used to calculate and analyze the thermal hydraulic parameters at the worst state during the lifetime of the reactor,which verified the safety of steadystate thermal hydraulic of the reactor core.The calculation results showed that MDNBR at steady-state is 3.485,the maximum temperature of the fuel rod cladding surface is187℃,the maximum temperature of the fuel pellet center is 1 902 ℃,which have proved that the thermal hydraulic parameters of reactor core can meet the safety requirements of the reactor,and leaves enough safety margins for accident conditions.更多还原