摘要
采用高温化学萃取法可以从反应堆辐照后的金属铋(^209Bi)中分离^210Po。设计了两种规格的金属铋靶件,用MCNP程序模拟靶件在中国先进研究堆(CARR)中的中子注量率及核发热情况,对两种靶件的传热进行计算。用氩弧焊对金属铋靶件进行焊接,对焊接后的靶件进行密封性检查。结果表明:两种靶件在CARR反应堆中满功率60 MW运行时中子注量率最大为5.21×10^14 n/cm^2·s,靶件总发热量分别为1707 W和2220 W,经传热计算后靶件中心温度分别为163.5℃和191.8℃,低于金属铋的熔点(271.3℃)。焊接后的靶件经密封性检查,泄漏率小于3.2×10^-9 Pa·m^3/s,金属铋靶件可用于CARR反应堆辐照制备^210Po核素。
High temperature chemical extract method can be used to separate^209 Bi and^210 Po in bismuth target after reactor irradiated.Two kinds of metal bismuth targets are designed.The MNCP program is used to simulate the neutron flux and nuclear heating in the CARR reactor,and the heat transfer of the two targets is calculated theoretically.The metal bismuth target is welded by argon,and the tightness of the welded target is checked.The results show that the maximum neutron flux rate of the two kinds of targets at the full power of 60 MW in the CARR reactor is 5.21×10^14 n/cm^2·s,the total heat output of the target is 1707 W and 2220 W respectively,and the center temperature of the targets is 163.5℃and 191.8℃respectively after heat transfer calculation,which is lower than the melting point of bismuth(271.3℃).The leakage rate of the welded target is less than 3.2×10^-9 Pa·m^3/s.Bismuth target can be used for the preparation of^210 Po nuclide by CARR reactor irradiation.
作者
杨红伟
向学琴
胡连生
马俊平
刘路
YANG Hongwei;XIANG Xueqin;HU Liansheng;MA Junping;LIU Lu(Department of Isotope,China Institute of Atomic Energy,Beijing 102413,China)
出处
《同位素》
CAS
2021年第1期66-70,I0005,共6页
Journal of Isotopes
作者简介
杨红伟(1978-),男,山西芮城人,高级工程师,主要从事放射源制备及放射性同位素相关研究。
