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 ›› 2017, Vol. 28 ›› Issue (3): 41 doi: 10.1007/s41365-017-0186-y

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Radionuclides in primary coolant of a fluoride salt-cooled hightemperature reactor during normal operation

Guo-Qing Zhang 1  Shuai Wang 1  Hai-Qing Zhang 1  Xing-Wang Zhu 1  Chao Peng 1,2  Jun Cai Zhao-Zhong He 1  Kun Chen 1   

  1. 1 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2 University of Chinese Academy of Sciences, Beijing 100049, China
  • Contact: Kun Chen E-mail:chenkun@sinap.ac.cn
  • Supported by:
    This work was supported by the “Strategic Priority Research Program” of the Chinese Academy of Sciences (No. XDA02050100) and the Scientific Research Foundation for the Returned Overseas Chinese Scholars, State Education Ministry (No. Y519011032).
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G.-Q. Zhang · S. Wang · H.-Q. Zhang · X.-W. Zhu · C. Peng · J. Cai · Z.-Z. He · K. Chen. Radionuclides in primary coolant of a fluoride salt-cooled hightemperature reactor during normal operation.Nuclear Science and Techniques, 2017, 28(3): 41     doi: 10.1007/s41365-017-0186-y

Abstract:

The release of fission products from coated particle fuel to primary coolant, as well as the activation of coolant and impurities, were analysed for a fluoride saltcooled
high-temperature reactor (FHR) system, and the activity of radionuclides accumulated in the coolant during normal operation was calculated. The release rate (release
fraction per unit time) of fission products was calculated with STACY code, which is modelled mainly based on the Fick’s law, while the activation of coolant and impurities
was calculated with SCALE code. The accumulation of radionuclides in the coolant has been calculated with a simplified model, which is generally a time integration
considering the generation and decay of radionuclides. The results show that activation products are the dominant gamma source in the primary coolant system during normal operation of the FHR while fission products become the dominant source after shutdown. In operation condition, health-impacts related nuclides such as 3H, and 14C originate from the activation of lithium and coolant impurities including carbon, nitrogen, and oxygen. According to the calculated effective cross sections of neutron activation,
6Li and 14N are the dominant 3H production source and 14C production source, respectively. Considering the high production rate, 3H and 14C should be treated before being released to the environment.

Key words: Source term, FHR, Primary coolant, Fick’s law, Diffusion