锶-90同位素放射源屏蔽结构设计  

Shielding Structure Design of ^(90)Sr Isotope Radiation Source

作　　者：马俊平 何虎[1] 罗志福[1] 

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《同位素》2017年第4期243-248,共6页Journal of Isotopes

摘　　要：在^(90)Sr放射源结构设计基础上,利用Monte Carlo程序MCNPX计算^(90)SrTiO_3陶瓷源表面的轫致辐射能谱和放射源外空间的剂量当量分布情况,并计算和设计屏蔽层。结果表明,90SrTiO_3陶瓷放射源表面的平均光子通量率约1.2×10^(10)cm^(-2)·s^(-1),表面最小剂量当量率约20Sv/h;应用厚度为7cm的钨材料屏蔽后,表面和1m处最大剂量当量率分别约为1.35mSv/h和0.027mSv/h,满足放射源运输要求。The bremsstrahlung spectrum on the surface of a ^90SrTiO3 ceramic radiation source was computed by using MCNPX on the base of the designed structure of the 90 Sr radioactive source.The distribution of the dose equivalent was calculated and analyzed.The results showed that the average photon flux was 1.2×10^10cm^-2·s^-1 on the surface of the radiation source,and the minimum dose equivalent rate of the surface was 20 Sv/h.By using 7 cm tungsten as the shielding structure,the maximum dose equivalent was 1.35 mSv/h on the surface and 0.027 mSv/h at 1 mbelow the surface.So the shielding material and structure designed meet the limit of radiation dose equivalent during the transportation.

关 键 词：^90SrTiO3 轫致辐射 剂量当量 屏蔽 

分 类 号：TL364.5[核科学技术—核技术及应用]