Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (9): 123 doi: 10.1007/s41365-018-0472-3

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal

Feng Gou, Yuan Liu, Fu-Bing Chen, Yu-Jie Dong   

  1. 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, Beijing 100084, China
  • Contact: Fu-Bing Chen E-mail:chenfubing@tsinghua.edu.cn
  • Supported by:

    This work was supported by the Chinese National S&T Major Project (No. ZX069).

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Feng Gou, Yuan Liu, Fu-Bing Chen, Yu-Jie Dong. Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal.Nuclear Science and Techniques, 2018, 29(9): 123     doi: 10.1007/s41365-018-0472-3

Abstract:

Two tests initiated by unscrammed control rod withdrawal were performed on the High Temperature Gas- Cooled Reactor-Test Module (HTR-10) in November 2003 after the reactor achieved its full power, and the test conditions represented a typical transient scenario of modular high-temperature reactors (HTRs), called pressurized loss of forced cooling, and anticipated transient without scram. Based on the test parameters, the HTR-10 thermal behaviors under the test conditions were studied with the help of the system analysis code THERMIX. The combination of the test results and the investigation results makes the HTR-10 safety potential better understood. Key phenomena, such as the helium natural circulation and the temperature redistribution in the reactor, were revealed. As the safety feature of most significance, there is a large margin between the maximum fuel temperature and its safety limit in each test. Temperatures of thermocouples in different components were calculated by THERMIX and compared with the test values. The applicability of the code was verified by good agreement obtained from the comparison.

Key words: HTR-10, Control rod withdrawal, ATWS, THERMIX