低、中放固体废物处置设施的屏蔽计算  

Shielding Calculation for Low-and-intermediate Level Radioactive Waste Disposal Facilities

作　　者：谢占军 

机构地区：[1]中核第四研究设计工程有限公司,石家庄050021

出　　处：《辐射防护通讯》2016年第6期11-15,共5页Radiation Protection Bulletin

摘　　要：天然屏障和工程屏障相结合的多重屏障设计是近地表低、中放固体废物处置场设计的基本原则。本文从辐射防护角度出发,对某低中放固体废物处置场处置单元的设计进行论证。分别采用点核积分法程序QAD和蒙特卡罗法程序MCNP,对处置单元格不同厚度墙体外的剂量率水平进行计算,确定出合理的处置单元构筑物墙体厚度,并得出两种屏蔽计算方法的适用范围。For the design of near surface low-and-intermediate level radioactive waste repository, the principle of multi barriers, which considering both natural and engineered barriers, should be held. From the point of view of radioproteetion, the design of a low-and-intermediate level radioactive waste disposal unit is demon- strated. Point kernel integration method QAD and Monte Carlo method MCNP were used to calculate the dose rate outside the walls with different thickness of disposal unit. Based on the calculation, the proper thickness of disposal unit wall was decided, and the application scope of each method was worked out.

关 键 词：低、中放废物处置 处置单元 屏蔽 QAD MCNP 

分 类 号：TL941.3[核科学技术—辐射防护及环境保护]