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

作　　者：Chao Peng Xing-Wang Zhu Guo-Qing Zhang Zhao-Zhong He Kun Chen 

机构地区：[1]Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China [2]University of Chinese Academy of Sciences, Beijing 100049,China

出　　处：《Nuclear Science and Techniques》2016年第2期149-154,共6页核技术（英文）

基　　金：Supported by the ‘‘Strategic Priority Research Program’’ of the Chinese Academy of Sciences(Grant No.XDA02050100)

摘　　要：The fluoride salt-cooled high-temperature reactor(FHR) uses molten FLi Be 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 MW th 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^(28) Al,^(60m) Co,^(56) Mn,^(51)Ti, and ^(52) V, as well as long-lived ^(60) Co,^(51)Cr,^(55)Fe,^(59)Fe, and ^(54) Mn.Furthermore, because of their relatively long half-life and high-energy c-rays emissions,^(60) Co and ^(54)Mn are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of ^(60)Co and ^(54)Mn per unit mass of alloy-N under the current core design is 5.58*10~5 and 1.55 * 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.The fluoride salt-cooled high-temperature reactor（FHR） uses molten FLi Be 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 MW th 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^（28） Al,^（60m） Co,^（56） Mn,^（51）Ti, and ^（52） V, as well as long-lived ^（60） Co,^（51）Cr,^（55）Fe,^（59）Fe, and ^（54） Mn.Furthermore, because of their relatively long half-life and high-energy c-rays emissions,^（60） Co and ^（54）Mn are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of ^（60）Co and ^（54）Mn per unit mass of alloy-N under the current core design is 5.58＊10~5 and 1.55 ＊ 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.

关 键 词：数值分析 反应堆容器 辐照 腐蚀作用 辐射防护 辐射源项 反应堆退役 结构材料 

分 类 号：TL426[核科学技术—核技术及应用]