Dynamic Analysis of Simulated Loss of Forced Cooling Tests on the HTR-10
As a part of the safety demonstration tests of the HTR-10, two simulated loss of forced cooling (LOFC) tests were performed to demonstrate that a rapid decrease of the primary coolant flow rate brings about a self-shutdown of the reactor merely due to the negative temperature coefficient of reactivity. The first test was conducted at 30% rated power, i.e., 3 MW power level in October, 2003 and the second one was carried out at 100% rated power, i.e., 10 MW power level in July, 2005. In this paper, transient behaviour of the HTR-10 during the simulated LOFC tests is simulated by using the THERMIX code system. The analytical and test results demonstrate the inherent safety features of the HTR-10 that the reactor can be shut down only by the negative temperature feedback after the stop of the helium circulator. The subsequent phenomena such as the recriticality of the reactor and the power oscillations are investigated. For each of the tests, THERMIX reproduces the power transition reasonably and accurately. Due to the large heat capacity of the reactor core and internals, the maximum fuel center temperature during each test is always lower than 1230 ℃ which is the limited value at the first phase of the HTR-10 project.
HTR-10 Loss of Forced Cooling Test THERMIX
Chen Fubing Dong Yujie Zhang Zuoyi Hu Shouyin Zhou Yangping Zheng Yanhua Shi Lei
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
国际会议
ISSNP2008、CSEPC、ISOFIC2008(第二届21世纪和谐核电系统国际会议、第四届电厂控制中认知系统工程方法国际会议暨第三届未来核电厂仪表与控制国际会议)
哈尔滨
英文
266-272
2008-09-08（万方平台首次上网日期，不代表论文的发表时间）