博碩士論文 106356003 詳細資訊




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姓名 邱筠捷(Yun-Chieh Chiu)  查詢紙本館藏   畢業系所 環境工程研究所在職專班
論文名稱 不同緩衝材料對核種之遷移及遲滯效能研究
(Function for Retard Nuclides Migration of different buffer materials)
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摘要(中) 於用過核子燃料最終處置設施中,緩衝材料應阻止地下水或腐蝕物質直接接觸廢棄物罐,並且延緩放射性核種向生物圈遷移之速度,達到滯遲(retardation)核種遷移之效果。緩衝材料之成分與規格將直接影響其滯遲能力,本研究以MX-80膨潤土、SWy-2 鈉型蒙脫石及蒙脫石含量20%至100%之調配材料為標的,考量緩衝材料成分、壓實乾密度及溫度條件之影響,量測不同規格緩衝材料之回脹壓力、水力傳導度及不同材料對Cs+與Sr2+核種吸附能力。
MX-80膨潤土於乾密度1,300 kg/m3至1,600 kg/m3條件之回脹壓力介於964 kPa至6,767 kPa之間,隨著乾密度增加而上升;水利傳導度則隨著試體乾密度提升而降低,約介於10-15 m/s至10-12 m/s之間;環境溫度從30°C升溫至60°C及 90°C時,緩衝材料試體之水力傳導度會隨著溫度上升而增加。此外,藉由不同SWy-2 鈉型蒙脫石配比土樣之回脹及水力傳試驗結果,單位緩衝材料中之蒙脫石含量與回脹壓力呈正比,且與水力傳導度呈反比。
吸附實驗結果顯示,MX-80膨潤土及不同SWy-2 鈉型蒙脫石配比土樣對Cs+及Sr2+之吸附行為皆符合Langmuir等溫吸附曲線,各土樣對Cs+之飽和吸附量皆大於Sr2+,而飽和吸附量則與土壤之蒙脫石含量呈正比。故高蒙脫石含量之材料選擇及高設計乾密度有利於滯遲核種向外遷移之效果。
摘要(英) In the final disposal facilities for spent nuclear fuel, buffer plays a role of barrier which not only prevents canister from directly exposing to groundwater and corrosive materials but also retards the migration of radial nuclides to biosphere. The “retardation” process is derived by the composition and specification of buffer. MX-80 bentonite, SWy-2 Na-montmorillonite and blended soil (20%~100% montmorillonite) were used in this research. The objective of this paper is to survey the swelling pressure, hydraulic conductivities, and nuclide (Cs+ and Sr2+) adsorption capacities of different buffer materials and specifications under different temperature conditions.
Swelling pressure and hydraulic conductivities of MX-80 bentonite with dry densities 1,300 kg/m3 ~1,500 kg/m3 were 964 kPa~6,67 kPa and 10-15 m/s ~10-12 m/s respectively; the swelling pressure increased as dry density increased while the hydraulic conductivity decreased as dry density increased. During the heating process, i.e. from 30°C to 60°C and 90°C, the hydraulic conductivity increased with increasing temperature. In addition, swelling pressure was proportional to, and hydraulic conductivity was inversely proportional to the montmorillonite content of soil.
The results of the adsorption experiment using the soil with different content of montmorillonite as sorbent indicated that both adsorption behaviors of Cs+ and Sr2+ are consistent with the Langmuir isotherm model. The adsorption capacity of Cs+ was larger than Sr2+, and the maximum adsorption capacities were proportional to the montmorillonite content in the soil. It was concluded that the selection of soil with high content of montmorillonite and high dry density as buffer materials could conduce to better retardation capability of nuclide migration.
關鍵字(中) ★ 緩衝材料
★ 回脹壓力
★ 水力傳導度
★ 銫
★ 鍶
★ 吸附
關鍵字(英) ★ buffer
★ swelling pressure
★ hydraulic conductivity
★ cesium
★ strontium
★ adsorption
論文目次 第 1 章 前言 1
1-1 研究緣起 1
1-2 研究目的 4
第 2 章 文獻回顧 6
2-1 用過核子燃料簡介 6
2-1-1 國內用過核子燃料概況 7
2-1-2 用過核子燃料特性 9
2-2 國內外相關管制法規 9
2-2-1 國際法規 10
2-2-2 國內管制法規 14
2-3 用過核子燃料最終處置技術 15
2-3-1 深層地質處置 17
2-3-2 深鑽孔處置 20
2-4 緩衝材料特性 24
2-4-1 膨潤土 25
2-4-2 高嶺土 26
2-4-3 雲母 27
2-4-4 蛭石 28
第 3 章 研究設備與方法 30
3-1 研究內容與流程 30
3-2 實驗材料 32
3-2-1 MX-80膨潤土 32
3-2-2 鈉型蒙脫石 32
3-2-3 渥太華標準砂 32
3-2-4 藥品 33
3-3 實驗設備與儀器 33
3-3-1 實驗設備 33
3-3-2 實驗儀器 34
3-4 試驗方法 41
3-4-1 元素分析(XRF) 41
3-4-2 礦物分析(XRD) 42
3-4-3 比表面積分析(BET) 42
3-4-4 試體製備 43
3-4-5 回脹試驗 46
3-4-6 水力傳導試驗 47
3-4-7 吸附試驗 48
第 4 章 結果與討論 49
4-1 緩衝材料基本理化特性分析 49
4-1-1 元素分析 49
4-1-2 礦物組成分析 50
4-1-3 比表面積、平均孔徑與孔徑分佈分析 52
4-1-4 有機碳含量 58
4-2 回脹壓力 59
4-2-1 試體密度對回脹壓力之影響 60
4-2-2 溫度對回脹壓力之影響 67
4-2-3 不同蒙脫石含量對回脹壓力之影響 70
4-3 水力傳導度 74
4-3-1 試體密度對水力傳導度之影響 74
4-3-2 溫度對水力傳導度之影響 77
4-3-3 不同蒙脫石含量對水力傳導度之影響 80
4-4 核種吸附特性 83
4-4-1 MX-80膨潤土 84
4-4-2 SWy-2 鈉型蒙脫石 88
4-4-3 不同蒙脫石比例對核種吸附之影響 91
第 5 章 結論與建議 97
5-1 結論 97
5-2 建議 98
參考文獻 100
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指導教授 李俊福(Jiunn-Fwu Lee) 審核日期 2019-7-26
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