【作者】 张冉； 郭凯伦； 王成龙； 张大林； 秋穗正； 苏光辉；

【Author】 ZHANG Ran;GUO Kailun;WANG Chenglong;ZHANG Dalin;QIU Suizheng;SU Guanghui;School of Nuclear Science and Technology, Xi’an Jiaotong University;State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University;

【机构】 西安交通大学核科学与技术学院； 西安交通大学动力工程多相流国家重点实验室；

【摘要】 空间核电源是空间核动力系统不可或缺的一部分,本文针对高温气冷快堆结合闭式布雷顿循环发电的大功率空间核动力系统,考虑反应堆、涡轮-压气机-发电机、回热器、气体冷却器、辐射散热器、泵及相应管道模型,采用Fortran语言开发了一套瞬态系统分析程序。通过程序稳态计算值与设计值的对比,验证程序的模型,进而对系统的典型事故工况进行瞬态分析,包括单个布雷顿环路机械故障和堆芯反应性意外引入事故。结果表明,由于燃料元件及堆芯基体的负反应性反馈,系统具有一定的安全性,堆芯燃料峰值温度在安全限值范围内。更多还原

【Abstract】 Space nuclear power is an integral part of space nuclear power systems. For the high-power space nuclear power, the high-temperature gas-cooled reactor combined with Closed Brayton Cycle(CBC), a transient analysis code is developed using Fortran. The reactor, turbine-compressor-alternator, recuperator, gas cooler, radiator, pump and pipe models are built and adopted in the code. The model is verified by the comparison between the steady state calculated value and the design value. The transient analysis under the accident conditions of the system is carried out, including mechanical failure in one Brayton loop and the accidental introduction of core reactivity. The results show that the system has certain safety due to the negative reactivity feedback of the fuel and the core block, and the fuel peak temperature is within the safety limit.更多还原