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研究生:鍾柏仁
研究生(外文):Bor-Ran Chung
論文名稱:核廢料深層處置近場岩石熱力學行為初步研究
論文名稱(外文):Thermo-Mechanical Properties of Near Field Rocks on the Geological Disposal for Nuclear Waste
指導教授:陳昭旭陳昭旭引用關係
指導教授(外文):Chao-Shi Chen
學位類別:碩士
校院名稱:國立成功大學
系所名稱:資源工程學系碩博士班
學門:工程學門
學類:材料工程學類
論文種類:學術論文
論文出版年:2002
畢業學年度:90
語文別:中文
論文頁數:140
中文關鍵詞:核廢料深層處置用過核燃料FLAC 3D
外文關鍵詞:spent unclear fuelFLAC 3Dgeological disposal
相關次數:
  • 被引用被引用:25
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  • 下載下載:95
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用過核燃料含有核分裂產物及長半衰期之放射性物質,對人類及生活環境具有潛在性危險,須採取與人類生活環境長期隔離方式處理。經過技術、經濟、安全等多層面之評估與相關研究顯示,目前以深層地質處置(Deep Geologic Disposal)方式來處理用過核燃料或高放射性廢料被認為較穩定且安全之措施。
本研究以核廢料深層處置為基本概念,並參考瑞典之相關研究,考慮膨潤土與回填材料所具備之熱性質及力學特性,藉由FLAC3D 數值分析軟體分析深覆蓋最終處置場之周圍岩體,於不同地溫之單孔處置坑、不同間距之雙孔處置坑及雙處置隧道等三種案例之形式,受核廢料罐所引起之溫度場與應力場影響後之發展行為。
經研究並多方面分析後認為於台灣地區500m 深之處置場中,可採用初始地溫為26∼28℃之結晶岩層,處置坑之間距為6∼8m 且處置隧道之間距為25℃較為適宜。而處置場址中拉力發生處多為其安全性與穩定性之依據,並於該發生區域須多採以補強之措施,以確保最終處置場址可持續其阻絕功能。
Because of its inherent radioactivity, spent nuclear fuel could cause the undesirable environmental effects. The spent nuclear fuel should be permanently excluded from human environment in order to avoid the danger that it could bring. From the aspects of technology, economy, and safety, throughout surveys indicate that the method of deep geologic disposal is regarded as the most stable and safest way in the disposal of spent nuclear fuel.
Based upon the concept of deep geological disposal proposed by Swedish research groups, this thesis takes the thermal and mechanical properties of the bentonite and backfill into consideration. Using the numerical analysis package FLAC3D, this thesis attempts to analyze the distributions of the temperature and mechanical fields of the geological repository disturbed by waste canisters. Several scenarios are taken into account: a single storage hole of different initial temperatures, and two-storage-hole and two-tunnel of different distances. In this study, the in-situ stress is considered 500m deep.
This thesis suggests that the appropriate distances from canister to canister are 6~8m and those from tunnel to tunnel are 25m under the conditions of initial temperature 26∼28℃ and 500m in-situ in Taiwan crystalline bedrock. Through stress analysis, this study shows that the
tensile regions are the most critical ones where should be reinforced to ensure the capability of isolation of the disposal site.
摘要... ...................................................................................................... Ⅰ
英文摘要.................................................................................................. Ⅱ
致謝... ...................................................................................................... Ⅲ
目錄... ...................................................................................................... Ⅳ
表目錄...................................................................................................... Ⅶ
符號定義.................................................................................................. Ⅷ
圖目錄...................................................................................................... XV
第一章緒論.............................................................................................. 1
1.1 前言............................................................................................. 1
1.2 研究目的..................................................................................... 2
1.3 研究內容..................................................................................... 3
第二章文獻回顧...................................................................................... 5
2.1 岩石之熱應力分析..................................................................... 5
2.1.1 岩石之溫度效應............................................................... 7
2.1.2 深層處置之相關研究...................................................... 8
2.2 岩石之基本熱力學性質........................................................... 13
2.3 核廢料處置概念....................................................................... 20
2.3.1 高放射性與低放射性廢料............................................ 20
2.3.2 處置方式........................................................................ 22
2.3.3 放射性核廢料處置流程與原則................................... 24
2.3.4 最終處置規劃................................................................ 30
V
2.3.5 多重屏障........................................................................ 33
2.3.6 處置場之選址準則........................................................ 38
第三章理論與數值分析方法................................................. 42
3.1 熱傳導理論............................................................................... 44
3.2 FDM 之數值熱傳導理論概述................................................. 47
3.2.1 以微分方程式推導........................................................ 47
3.2.2 以能量平衡推導........................................................... 48
3.2.3 能量方程式微分推導..................................................... 50
3.3 數值分析方法........................................................................... 53
3.3.1 FLAC3D 概述.................................................................. 53
3.3.2 FLAC3D 運算程序.......................................................... 56
3.3.3 FLAC3D 熱傳模式之特點.............................................. 57
3.3.4 FLAC3D 熱傳模式基本原理.......................................... 58
3.3.5 FLAC3D 之基本分析架構.............................................. 71
3.3.6 FLAC3D 之實際分析步驟.............................................. 73
第四章案例驗証與模擬分析................................................................ 75
4.1 程式驗證模擬........................................................................... 75
4.2 深層岩石熱力學性質模擬分析.............................................. 88
4.2.1 數值模擬之假設與參數選擇....................................... 88
第五章核廢料罐處置坑之數值模擬分析......................................... 107
5.1 案例形式.................................................................................. 107
5.1.1 單處置坑....................................................................... 107
5.1.2 雙處置坑....................................................................... 108
5.1.3 雙處置隧道................................................................... 108
5.2 結果討論.................................................................................. 109
5.2.1 溫度分佈...................................................................... 110
5.2.2 x 向水平應力分佈..................................................... 117
5.2.3 y 向水平應力分佈..................................................... 120
5.2.4 垂直應力分佈.............................................................. 122
5.2.5 處置坑塑性分佈.......................................................... 125
5.2.6 處置坑岩體位移方向.................................................. 126
第六章結論與建議.............................................................................. 131
6.1 結論......................................................................................... 131
6.2 建議......................................................................................... 134
參考文獻................................................................................................ 135
附錄A 處置坑之二維溫度分布(1.5 year)..........................................A-1
附錄B 處置坑之三維溫度分布(1.5 year).......................................... B-1
附錄C 平行x 軸之水平應力分布(1.5 year) ..................................... C-1
附錄D 平行y 軸之水平應力分布(1.5 year) .....................................D-1
附錄E 垂直應力分布(1.5 year).......................................................... E-1
附錄F 處置坑塑性區分布(1.5 year) .................................................. F-1
附錄G 處置坑岩體之位移方向(1.5 year) .........................................G-1
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