花岗岩中高放废物地质处置库系统分析方法研究  

System analysis methods for geological repository of high level radioactive waste in granite

作　　者：陈伟明[1] 王驹[1] 李云峰[1] 金远新[1] 赵宏刚[1] 

机构地区：[1]核工业北京地质研究院,北京100029

出　　处：《世界核地质科学》2009年第3期160-166,共7页World Nuclear Geoscience

摘　　要：首先以甘肃北山预选区花岗岩场址为例,提出该场址中高放废物地质处置库概念设计和结构设计,然后以系统分析方法论为基础,描述处置库的系统功能、结构、环境及其演化过程,并以模拟软件GoldSim为工具,建立该处置库演化过程的计算机模型,最后以该计算机模型为模拟实验平台,模拟处置库中辐射毒性时空分布,分析模型中的参数灵敏度,优化设计参数,并预测和评价处置库性能。其研究成果可为合理配置资源和有效协调各研究项目之间关系提供技术支持。Taking Beishan granite site as an example, this paper proposes the conceptual and structural design of repository for high level radioactive waste at first. Then the function, structure, environment and evolution of the repository are described by the methodology of system analysis. Based on these designs and descriptions, a calculation model for the repository is developed with software GoldSim. At last, this calculation model is applied to emulate the space-time distribution of repository radiotoxicity, to analyze the sensitivity of parameters in the model, to optimize the design parameters, and to predict and assess the repository performance. The results of this study can provide technical supports for resources allocation and coordination of R＆D projects.

关 键 词：系统分析 高放废物 处置库 性能评价 北山 

分 类 号：TL942.1[核科学技术—辐射防护及环境保护]