摘要
本文主要应用蒙特卡罗方法进行了屏蔽计算的研究。在开展蒙特卡罗方法的实际应用中,对大亚湾第一炉换料乏燃料运输容器进行了屏蔽计算。源项应用ORIGEN-Ⅱ程序的计算结果,应用MCNP程序对乏燃料运输容器(STC)进行屏蔽计算,并将计算结果与实测值进行了比较分析。考虑到今后可能会运输更高燃耗的乏燃料,本文对这类乏燃料的运输也进行了计算。
This paper is devoted to the research on the radiation shielding calculations using Monte Carlo method. MCNP code is used in the shielding calculation for the spent fuel transport cask （STC） containing directly loaded spent fuel assemblies of Daya Bay NPP （ the source term is calculated by the ORIGEN-Ⅱ code）. The results are compared with measuring results. Considering that the spent fuel with high bumup will be transported in the future, the radiation shielding for those spent fuel are calculated as well.
出处
《辐射防护》
CAS
CSCD
北大核心
2007年第2期65-71,共7页
Radiation Protection
