CHAPTER IX:THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE
CHAPTER IX: THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE
New words and phrases high-level radioactive waste(HLW)）高放射性废物 byproduct副产品 reactor核电站，反应堆 nuclear fission products核裂变产物 glass matrix玻璃基体 vitrification玻璃化 vitrified solids玻璃状物体 decay衰减 transuranic(TRU)超铀的 alpha particles阿尔法粒子 vaults地下室 glaciated areas冰封地区
New words and phrases high-level radioactive waste (HLW) 高放射性废物 byproduct 副产品 reactor 核电站，反应堆 nuclear fission products 核裂变产物 glass matrix 玻璃基体 vitrification 玻璃化 vitrified solids 玻璃状物体 decay 衰减 transuranic (TRU) 超铀的 alpha particles 阿尔法粒子 vaults 地下室 glaciated areas 冰封地区
New words and phrases ocean floor海床 extra terrestrial disposal外太空处理 radionuclide放射性核素 leach-resistant抗浸析 corrosion-resistant containers抗腐蚀容器 backfill回填 circulating groundwater地下水循环 repository储藏室，处置库 depth of burial埋藏深度 flexibility适应性，机动性
New words and phrases ocean floor 海床 extra terrestrial disposal 外太空处理 radionuclide 放射性核素 leach-resistant 抗浸析 corrosion-resistant containers 抗腐蚀容器 backfill 回填 circulating groundwater 地下水循环 repository 储藏室，处置库 depth of burial 埋藏深度 flexibility适应性，机动性
New words and phrases rock salt岩盐 argillaceous formations(clays)泥质，粘土质地层 crystalline rock结晶岩 granite花岗石 welded tuff熔结凝灰岩 metamorphic rock变质岩 sub-seabed disposal海底沉积 unconsolidated sediments未固结沉积物 underlying下伏的 consolidated sediments固结沉积物 emplacement technology就位技术
New words and phrases rock salt 岩盐 argillaceous formations (clays) 泥质，粘土质地层 crystalline rock 结晶岩 granite 花岗石 welded tuff 熔结凝灰岩 metamorphic rock 变质岩 sub-seabed disposal 海底沉积 unconsolidated sediments未固结沉积物 underlying 下伏的 consolidated sediments 固结沉积物 emplacement technology 就位技术
New words and phrases dilution capacity稀释能力 high sea公海 sealed密封 OECD:Organization for Economic Cooperation and Development 经济合作与发展组织[欧洲扪 polluter pays principle污染人赔款原则 Nuclear Energy Agency核能源署 interplay相互作用 bilateral cooperative双边合作 probabilistic events概率事件 geosphere岩石圈 validation有效性
New words and phrases dilution capacity 稀释能力 high sea 公海 sealed 密封 OECD: Organization for Economic Cooperation and Development 经济合作与发展组织[欧洲] polluter pays principle 污染人赔款原则 Nuclear Energy Agency 核能源署 interplay 相互作用 bilateral cooperative 双边合作 probabilistic events 概率事件 geosphere 岩石圈 validation 有效性
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)