首页> 外文会议>International symposium on unsaturated soil mechanics and deep geological nuclear waste disposal >LONG-TERM SAFETY ANALYSIS AND MODEL VALIDATION THROUGH URL RESEARCH-A MAJOR TASK OF GRS' FINAL REPOSITORY RESEARCH DIVISION
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LONG-TERM SAFETY ANALYSIS AND MODEL VALIDATION THROUGH URL RESEARCH-A MAJOR TASK OF GRS' FINAL REPOSITORY RESEARCH DIVISION

机译:通过URL研究进行长期安全性分析和模型验证-GRS最终仓储研究部门的主要任务

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In Germany all types of radioactive waste will be disposed of in deep geological repositories. While a repository for low-level radioactive waste (LLW) has recently been licensed, different host rock formations are considered for disposal of heat producing high-level waste (HLW). The latter includes directly disposed spent fuel and vitrified waste from its reprocessing. Different canister and disposal concepts are considered for spent fuel disposal, i.e. thick-walled iron casks in horizontal drifts or thinwalled BSK3 steel casks in vertical boreholes, respectively. GRS is the leading expert institution in Germany concerning nuclear safety and waste management Since 30 years, GRS has developed and continuously improves a set of computer codes, which allow to assess the performance and the long-terM safety of repositories in various host rocks (salt, clay or granite) applying different technical options. Advanced methods for deterministic as well as probabilistic assessments are available. In order to characterize the host rocks and backfill/buffer materials and to develop disposal technologies, comprehensive laboratory experiments and a large number of in-situ tests have been performed at GRS' geo-laboratory and at underground research laboratories in different host formations. THMc processes occurring in the host rocks and engineeredbarrier-systems are numerically simulated. The paper presents an overview of GRS' work highlighting important results of PA studies for both the salt option and the clay option. Also, recent results of in-situ investigations and laboratory studies will be presented together with modeling results. Special emphasis is dedicated to the consideration of coupled tHM processes which are of relevance in PA.
机译:在德国,所有类型的放射性废物都将在深层地质处置库中处置。虽然最近已批准了低放射性废物(LLW)的存储库,但考虑使用不同的宿主岩层来处置产生热量的高水平废物(HLW)。后者包括直接处置的乏燃料和来自其后处理的玻璃化废物。考虑使用不同的罐和处置概念来处理乏燃料,即分别在水平井巷中使用厚壁铁桶或在垂直井眼中使用BSK3型薄壁钢桶。 GRS是德国在核安全和废物管理方面的领先专家机构。自30年来,GRS已开发并不断改进一套计算机代码,这些代码可用于评估各种主岩层(盐)的储存库的性能和长期安全性。 ,粘土或花岗岩)应用不同的技术选择。可以使用确定性和概率评估的高级方法。为了表征基质岩石和回填/缓冲材料并开发处置技术,已在GRS的地质实验室和地下研究实验室中不同基质中进行了全面的实验室实验和大量现场测试。数值模拟了在母岩和工程屏障系统中发生的THMc过程。本文概述了GRS的工作,重点介绍了盐和黏土选项的PA研究的重要结果。此外,还将提供现场调查和实验室研究的最新结果以及建模结果。特别强调专门考虑与PA相关的耦合tHM工艺。

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