【作者】 陈福冰； 董玉杰； 张作义； 郑艳华； 石磊； 李富；

【Author】 Chen Fubing;Dong Yujie;Zhang Zuoyi;Zheng Yanhua;Shi Lei;Li Fu;Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education;

【机构】 清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室；

【摘要】 10 MW高温气冷实验堆(HTR-10)是我国第一座模块式高温气冷堆。反应性变化试验是HTR-10的三个动态特性试验之一,该试验不仅证明了反应堆的功率自调节性能,也为系统分析程序的验证提供了实测数据。基于实际的试验工况,利用THERMIX程序对反应性变化试验进行了模拟,分析了反应堆主要参数的变化。对于反应堆功率,计算结果与试验结果符合得很好,证明程序能够满意地再现HTR-10在该试验中的动态特性。试验过程中,燃料元件中心最高温度始终低于1230℃的温度限值。更多还原

【Abstract】 The 10 MW High Temperature Gas-cooled Reactor-Test Module(HTR-10) is the first high temperature gas-cooled reactor in China. The reactivity variation test is one of the three dynamic characteristic tests conducted on the HTR-10. This test not only verifies the HTR-10 self-adjustment capability for the reactor power, but also provides measured data for the validation of system analysis codes. Based on the actual test conditions, the reactivity variation test is simulated using the THERMIX code. Furthermore, main reactor parameters of interest are analyzed. The calculated reactor power agrees well with the test one, demonstrating that the THERMIX code can satisfactorily reproduce the HTR-10 dynamic characteristics during the reactivity variation test. During the test process, the maximum fuel center temperature is always below its limit value of 1230 ℃.更多还原