中国示范快堆常规岛图形建模与仿真分析  

Graphic Modeling and Simulation Analysis of China Demonstration Fast Reactor Conventional Island

作　　者：祁琳[1] 赵守智[1] 王晓坤[1] 于宏[1] 魏洪斌 张瑞鹏 

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413 [2]北京诺思维信科技有限公司,北京100085

出　　处：《原子能科学技术》2017年第11期1982-1988,共7页Atomic Energy Science and Technology

摘　　要：为研究中国示范快堆电厂的运行工况,在vPower平台上建立了中国示范快堆电厂常规岛的热力学系统仿真模型,并对常规岛的典型运行工况进行仿真计算。常规岛各稳态运行工况的仿真计算结果给出了运行的关键参数,这些关键参数与机组的设计参数相差不超过1%,达到了核电仿真的精度要求。高压给水加热器解列及汽轮机紧急停机工况的仿真计算结果给出了关键参数的变化规律以及可能的危险点信息。To investigate the operating conditions of China demonstration fast reactor power plant, the conventional island thermal system simulation model was established on the vPower platform, and then several typical operating conditions for conventional island were simulated. The operating key parameters of steady state operating conditions were given by simulations, and they are no more than 1% off the design values, which meet the demanded accuracy of nuclear power simulation. High-pressure feedwa- ter heater splitting and steam turbine emergency shutdown were simulated, and the transformation law of key parameter and information of the possible danger point were given.

关 键 词：中国示范快堆 常规岛系统 vPower 加热器解列 紧急停机 

分 类 号：TL48[核科学技术—核技术及应用]