1.What is high-level radioactive waste? 2.What are the differences between TRU waste and HLW? 3.What options are available for HLW disposal? 4.What are the basic requirements for a geological formation used in the disposal of HLW? 5.What are the important reasons why deep geological disposal on land has evolved into the disposal method of choice for virtually every country with a nuclear power programmer? 6.What happens to HLW during disposal? 7.How can the safety of HLW disposal be assessed?
1. What is high-level radioactive waste? 2. What are the differences between TRU waste and HLW? 3. What options are available for HLW disposal? 4.What are the basic requirements for a geological formation used in the disposal of HLW? 5.What are the important reasons why deep geological disposal on land has evolved into the disposal method of choice for virtually every country with a nuclear power programmer？ 6. What happens to HLW during disposal? 7. How can the safety of HLW disposal be assessed?
乏燃料 spent fuel ● ● ● ● ● 后处理 玻璃固化 vitrification 玻璃固化体 vitrified solids 处置库 repository
乏燃料 spent fuel 处置库 repository 后处理 玻璃固化体 vitrified solids 玻璃固化 vitrification
将高放废物封存在距地表以下一定深度的合适岩体中 的地下处置库内，通过人为设置种种屏障来阻止核素的泄 漏与迁移，达到对高放废物的安全处置。 installations Detail of dispofaciity ①Host rock ②Bentonite bacfill ③Cask 03 CONCEPTUAL SCHEME OF A DEEP GEOLOGICAL DISPOSAL (DGD) 缓冲/回填材料是指充填在废物包装容器与地质体之间、以及 联络通道内的封存材料，是处置库长期安全性和稳定性的有效保障
放射性废弃物的深地质处置示意图 将高放废物封存在距地表以下一定深度的合适岩体中 的地下处置库内，通过人为设置种种屏障来阻止核素的泄 漏与迁移，达到对高放废物的安全处置。 缓冲/回填材料是指充填在废物包装容器与地质体之间、以及 联络通道内的封存材料，是处置库长期安全性和稳定性的有效保障
1引言 研究背景 在热 Water/Gas Plug Granite migration 量、水压 力、应力 Access drift 00 和化学作 Gas Injection 用下，产 生“热 Concrete silo Gas migration 水-力-化 Construction joint (THMC)” Bentonite-sanc mixture 耦合现象。 04.0m High permeability shear zone
在 热 量 、水压 力 、应力 和化学作 用下 ， 产 生 “ 热 - 水 - 力 - 化 (THMC) ” 耦合现象 。 1引言 研究背景
日本处置库规划：2030建设处置库 Second Progress report(H12) 2040 R&D First Progress Repository report(H3) R&D by JNC,Tokai and URLs 2030 Operation 2020 Start in (2033-2037 Interim Report for 2010 Disposal Concept Licensing Construction 2000 (around 2025) Start of R&D 1992 Site Selection Program 1984 Characterization 1976 Definition of Safety Fundamentals Implementation Legislation of HLW Establishment of NUMO Final Disposal
Start of R&D Program 日本处置库规划：2030 建设处置库 Legislation of HLW Final Disposal 1976 2040 2020 2010 2000 2030 First Progress report (H3) 1992 R&D Implementation 1984 Interim Report for Disposal Concept Definition of Safety Fundamentals Establishment of NUMO Second Progress report (H12) Site Selection & Characterization Repository Operation Start in (2033 – 2037) Licensing & Construction (around 2025)