Thermal Response of the HTR-10 during Loss of Forced Cooling Test without Reactor Scram
The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10), designed, constructed and operated by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is the first High Temperature Gas-cooled Reactor (HTGR) in China. Following the first criticality in December, 2000, the HTR-10 achieved the full power operation in January, 2003. From then on, four safety demonstration tests, which belong to the simulation test of anticipated transient without scram (ATWS), have been successively performed to verify the inherent safety features of small modular HTGRs as well as to provide transient test data for the code validation work in INET. Among these tests, two loss of forced cooling (LOFC) ATWS tests were conducted by tripping the helium circulator without reactor scram. The first and second tests were carried out at 30％ rated power in October, 2003 and at 100％ rated power in July, 2005, respectively. In this study, thermal response of the HTR-10 during each LOFC ATWS test is simulated using the THERMIX code based on the actual operation parameters. After the initiation of each test, the reactor undergoes a self-shutdown owing to the combination of the negative temperature coefficient of reactivity and the core temperature rise resulting from the rapid decrease of the primary coolant flow rate. In the subsequent test period, the reactor becomes recritical due to no operation of the reactor shutdown system. In the absence of forced cooling, fission and decay heat from the reactor core are transferred to the residual heat removal system (RHRS) by conduction, radiation and natural convection. The consequent phenomena such as the temperature redistribution and natural circulation in the reactor core are investigated. Due to the large heat capacity of the HTR-10, the maximum fuel center temperature during each test does not exceed 1230 ℃, set as the temperature limit at the first phase of the HTR-10 project. The simulation results indicate the safety potential of the HTR-10 under such LOFC ATWS accident conditions.
HTR-10 THERMIX LOFC ATWS test thermal response
Fubing Chen Yujie Dong Yanhua Zheng Fu Li Zuoyi Zhang
Institute of Nuclear and New Energy Technology, Tsinghua University Energy Science Building, Tsinghua University, Beijing 100084, P. R. China
国际会议
上海
英文
2293-2308
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）