【作者】 高堃植； 侯哲； 赵升守； 陈焕栋； 张小英；

【Author】 GAO Kun-zhi;HOU Zhe;ZHAO Sheng-shou;CHEN Huan-dong;ZHANG Xiao-ying;School of Electricity,South China University of Technology;

【机构】 华南理工大学电力学院；

【摘要】 为得到反应堆瞬态运行的热工水力参数,本文建立了反应堆热工水力分析的子通道均匀流模型并编写了反应堆瞬态分析程序。程序通过对子通道模型中横向动量方程和轴向动量方程进行耦合提高程序的收敛速度和稳定性。为验证程序分析能力,本文首先应用程序计算文献提供的百万千瓦压水堆稳态算例,将得到的堆芯热组件的热工水力参数以及最小临界热流密度位置与算例结果进行对比。在堆芯稳态计算基础上引入反应堆功率骤升和冷却剂流量骤减的瞬态事故工况,计算得到堆芯典型组件的热工水力参数,并分析了组件热工水力参数的瞬态特性。计算和分析结果表明,建立的子通道模型和瞬态分析程序能够模拟百万千瓦压水堆瞬态特性。更多还原

【Abstract】 To investigate the transient hydraulic characteristics of nuclear reactors,a transient hydraulic analysis code based on sub-channel homogeneous flow model is developed.In order to shorten the saturation time and enhance the stability of the iteration,a coupling of transverse momentum equation with the axial ones is needed.The developed code is applied to a given millionkilowatt pressurized water reactor(PWR).Then the paper compares the output data with the one in the typical case so as to ensure the accuracy.In the case of accidental condition,in which the sharp changes are made to power and flow,occurred in the steady status,time-varying data is output and analyzed.As the data and analyses shown,it is appropriate for the transient hydraulic analysis code to simulate million-kilowatt PWRs.更多还原