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 ›› 2016, Vol. 27 ›› Issue (2): 44 doi: 10.1007/s41365-016-0044-3

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Numerical analysis of the activity of irradiated alloy-N in an FHR

Chao Peng, Xing-Wang Zhu, Guo-Qing Zhang, Zhao-Zhong He, Kun Chen   

  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
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Chao Peng, Xing-Wang Zhu, Guo-Qing Zhang, Zhao-Zhong He, Kun Chen. Numerical analysis of the activity of irradiated alloy-N in an FHR.Nuclear Science and Techniques, 2016, 27(2): 44     doi: 10.1007/s41365-016-0044-3

Abstract:

The fluoride salt-cooled high-temperature reactor (FHR) uses molten FLiBe salt as the coolant, which introduces a corrosive effect on the alloy-N structure material. Fission neutrons activate the corroded alloy-N, along with alloy-N structures inside the reactor vessel. The activation products of the alloy-N have a big impact on radiation protection during operation, maintenance, and decommissioning of the reactor. We have constructed a SCALE 6.1 model for the core of a typical 10 MWth FHR and analyzed the activity of each constituent of the irradiated alloy-N. The results show that the activity is predominantly due to short-lived 28Al, 60mCo, 56Mn, 51Ti, and 52V, as well as long-lived 60Co, 51Cr, 55Fe, 59Fe, and 54Mn. Furthermore, because of their relatively long half-life and high-energy γ-rays emissions, 60Co and 54Mn are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of 60Co and 54Mn per unit mass of alloy-N under the current core design is 5.58 × 105 and 1.55 × 103 Bq MWd?1 g?1, respectively. The results of this paper, combined with future corrosion studies, may provide a basis for evaluating long-term radiation source terms of the primary loop salt and components.

Key words: FHR, Alloy-N, Corrosion, Neutron activation, 60Co, TMSR