Chen, K (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
文章类型:
期刊文献
英文摘要:
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 Al-28, Co-60m, Mn-56, Ti-51, and V-52, as well as long-lived Co-60, Cr-51, Fe-55, Fe-59, and Mn-54. Furthermore, because of their relatively long half-life and high-energy gamma-rays emissions, Co-60 and Mn-54 are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of Co-60 and Mn-54 per unit mass of alloy-N under the current core design is 5.58 x 10(5) and 1.55 x 10(3) 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.
Peng, C,Zhu, XW,Zhang, GQ,et al. Numerical analysis of the activity of irradiated alloy-N in an FHR[J]. NUCLEAR SCIENCE AND TECHNIQUES,2016-01-01,27(2):—.
