MCNP程序对某坑式废物库贮存废物放射性活度验证计算  

MCNP Verification Calculation of Activity for Waste Stored in a Trap Repository

作　　者：马小强[1] 李兴义[1] 刘登奎[1] 

机构地区：[1]中国核动力研究设计院,四川成都610005

出　　处：《原子能科学技术》2010年第B09期583-586,共4页Atomic Energy Science and Technology

摘　　要：某废物库退役源项调查是废物库退役工程前期工作,为退役设计提供源项输入。根据现场辐射水平测量结果,利用点核积分原理,通过γ辐射水平与γ射线注量之间的关系,反推出废物的放射性活度。为评价计算结果,利用MCNP程序进行了验证计算。点核积分计算结果为6.4×1014Bq,MCNP验证计算结果为4.82×1014Bq,表明点核积分计算结果偏保守,满足工程设计需要。To offer the source for a trap repository decommissioning engineering, the activity of medium solid radioactive waste was calculated by point-kernel ray-tracing technique and the result is 6.4×1014 Bq. To appraise the result, a verification calculation was performed by MCNP and the result is 4.82×1014 Bq. It shows that point-kernel result is a little bigger than MCNP result. Therefore, point-kernel result is satisfied for engineering design.

关 键 词：放射性废物 活度 MCNP 验证计算 

分 类 号：TL942[核科学技术—辐射防护及环境保护]