中国实验快堆大泄漏反应事故模拟计算分析  

Simulation and Analysis of China Experimental Fast Reactor Large Leakage Reaction Accident

作　　者：王冲[1] 徐帅 朱桓君 WANG Chong;XU Shuai;ZHU Huanjun(China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《核科学与工程》2021年第3期631-638,共8页Nuclear Science and Engineering

摘　　要：大泄漏钠−水反应是钠冷快堆的设计基准事故,可能会导致二回路边界的破坏,导致放射性外泄,研究大泄漏钠水反应事故对反应堆安全分析具有重要的意义。本文建立了中国实验快堆大泄漏反应事故的计算分析模型,计算了反应区压力、反应区温度、二回路管道、重要设备中压力和流量以及缓冲罐气腔体积和缓冲罐钠液位增量等参数变化。将计算结果和中国实验快堆安全分析报告计算结果进行对比,验证了大泄漏钠水反应分析程序的正确性。The large leakage sodium water reaction is the design benchmark accident of the sodium-cooled fast reactor.It may lead to the destruction of the boundary of the secondary circuit and radioactive leakage.It is of great significance for reactor safety analysis to study the accident of large leakage sodium water reaction.A computational analysis model of China experimental fast reactor large leakage reaction was established in this paper.The reaction zone pressure,reaction zone temperature,secondary circuit pipeline,pressure and flow rate of important equipment,chamber volume and of sodium level increment of stabilization tank and other parameters were calculated.The calculated results were compared with the safety analysis report of China experimental fast reactor,and then the correctness of the large leakage sodium water analysis program was verified.

关 键 词：钠水反应 大泄漏 中国实验快堆 

分 类 号：TL364[核科学技术—核技术及应用]