KBS-3乏燃料包装容器表面中子剂量分布模拟分析  

Simulation and Analysis the Neutron Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP

作　　者：杨波[1,2] 吴和喜[2] 刘义保[1,2] 刘玉娟[2] 

机构地区：[1]东华理工大学放射性地质与勘探技术国防重点学科实验室,江西抚州344000 [2]东华理工大学核工程技术学院,江西抚州344000

出　　处：《东华理工大学学报（自然科学版）》2011年第2期160-164,共5页Journal of East China University of Technology(Natural Science)

基　　金：江西省自然科学基金(2009GZW0001);江西省教育厅科技项目(GJJ11149);东华理工大学校长基金(DHXK1021);东华理工大学放射性地质与勘探技术国防重点学科实验室开放基金项目(2010RGET10)

摘　　要：KBS-3乏燃料包装容器用于瑞典乏燃料地质处置,其内衬材料分成I24,I25和I26三类。乏燃料使处置库处于高强度放射场,包装容器表面的中子剂量分析对乏燃料包装容器运输、地质处置库剂量分析和地下水辐照分解有重要意义。采用MCNP程序模拟计算三种不同内衬材料(I24,I25和I26)包装容器表面的中子剂量分布,分析计算结果并为乏燃料包装容器内衬材料的选择提供参考。The KBS-3 canister for geological disposal of spent nuclear fuel in Sweden insert and a copper shielding. The ductile cast iron insert provides the mechanical consists of a ductile cast iron strength whereas the copper protects the canister from corrosion. The canister inserts material were referred to as I24, I25 and I26, Spent nuclear fuel make the repository in high radiant intensity. The radiation analysis of canister insert is important in canister transport, the dose analysis of repository and groundwater radiolysis. Groundwater radiolysis, which produces oxidants （H2O2 and 02 ）, will break the deep repository for spent nuclear fuel. The neutron dose distribution of canister surface with different kinds of canister inserts （ I24, I25and I26） is calculated by MCNP. Analysing the calculation results, we offer a referrence for selecting canister inserts material.

关 键 词：乏燃料包装容器 铸型铁内衬 MCNP 辐照分解 

分 类 号：O571.53[理学—粒子物理与原子核物理] TL249[理学—物理]