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研究生： 方昱傑
Yu-Jie Fan
論文名稱： 瑕疵處置罐壓力分析、處置隧道地震分析與處置罐剪力分析
指導教授： 張瑞宏
口試委員:
學位類別： 碩士
Master
系所名稱： 工學院 - 土木工程學系
Department of Civil Engineering
論文出版年： 2019
畢業學年度： 107
語文別： 中文
論文頁數： 117
中文關鍵詞： 用過核子燃料 、深地層處置 、瑕疵處置罐圍壓 、處置隧道開挖 、受震穩定分析
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    • 深地層處置是國際間多年研究共同認為最安全且可行的用過核子燃料處置方法。
    本文使用有限元素軟體Abaqus進行深地層處置概念進行瑕疵處置罐壓力分析、處置隧道斷面開挖與受震分析和處置罐剪力分析。
    在瑕疵處置罐壓力分析，參考瑞典SKB文獻建立處置罐模型，並進行瑕疵模擬，探討處置罐承受膨潤土回脹壓力與冰河時期的冰川負載環境下的影響並與文獻平行驗證，且進行瑕疵與分析方法之影響分析。結果判定本研究案例分析模型與文獻[1]模型近似，且瑕疵位置上進行雙向的剝離機制較接近參考案例結果。
    此外，在處置隧道斷面開挖與受震分析本文亦參考國內台電報告，建立二維模型模擬母岩內處置隧道開挖與利用動力分析下受震時之穩定分析，進而對於記錄點上進行主應力比較與文獻驗證，並進行邊界條件、地震加載方式與地震大小的機制影響分析。結果顯示受震與未受震對於處置隧道之主應力結果近乎相同。
    最後，在處置罐剪力分析本文透過瑞典SKB報告與台電報告等相關文獻研究深地層處置罐受剪力之應力分析。因相關文獻定義處置罐最大容許應力為395MPa，故本研究之剪力分析結果與其有1.22之安全餘裕。

    Deep geologic disposal is the most safe and feasibility of nuclear fuel final repository that have been evaluated and studied internationally.

    Use the finite element software ABAQUS to simulate pressure analysis of the defective disposal canister, disposal of tunnel section excavation and seismic analysis and analysis of canister shear force.

    In the pressure analysis of the defective disposal canister, the disposal canister model was established with reference to the Swedish SKB literature, and the defective simulation was carried out to investigate the effects of the disposal canister on the re-expansion pressure of the bentonite and the glacier load environment during the glacial period to verify with the literature, and carry out the impact analysis of the defect and analytical methods. As a result, counted the case analysis model of this study was similar to the literature model, and use the two-way delaminate mechanism at the defective position was closer to the reference case result.

    In addition, in the excavation and seismic analysis of the disposal tunnel section is also refers to the domestic Taiwan power company’s report, establishes a two-dimensional model to simulate the stability of the tunnel under the excavation and utilization of the dynamic analysis of the rock, and then compare the principle stress on the recorded point and literature verification. And the impact analysis of boundary conditions, seismic loading methods and earthquake size. The results show that the quaked and unquaked results are nearly identical for the principle stress of the disposal tunnel.

    Finally, in the analysis of the shear strength of the disposal canister, the present study the stress analysis of the shear force of the deep geologic disposal canister through the Swedish SKB report and the Taiwan power company’s report. The maximum allowable stress of the disposal canister is 395 MPa as defined by the relevant literature, so the shear analysis result of this study has a safety margin of 1.22.

    摘要 I ABSTRACT II 致謝 IV 圖目錄 VIII 表目錄 XI 第一章 緒論.............1 1.1 前言.............1 1.2 研究動機與目的.....2 1.3 研究主題與方法.....2 1.4 論文內容 ..........3 第二章 處置場概況與分析之相關文獻.........4 2.1 當前用過核子燃料最終處置方法.......4 2.2 我國最終處置推動之相關研究.........5 2.3 各國處置場概況...........8 2.3.1 瑞典....................8 2.3.2 芬蘭.........10 2.4 我國最終處置規劃與目標.........13 2.5 文獻研析.........15 第三章 瑕疵處置罐壓力分析.........37 3.1 前言.........37 3.2 處置罐之圍壓分析與瑞典SKB驗證.........37 3.3 模型尺寸建立.........38 3.4 材料參數.........40 3.5 初始條件與邊界條件.........41 3.6 分析結果.........43 3.7 剝離長度幾何影響分析.........46 3.8 剝離機制影響分析.........47 3.9 RIKS-弧長法影響分析.........50 3.9.1 RIKS分析方法.........50 3.9.2 RIKS位移控制之影響分析.........52 3.10 小結.........55 第四章 處置隧道地震分析.........56 4.1 前言.........56 4.2 隧道斷面開挖之穩定分析.........56 4.2.1 模型幾何介紹.........57 4.2.2 材料參數.........58 4.2.3 初始條件及邊界條件.........59 4.2.4 分析結果.........60 4.2.5 邊界條件機制之影響分析.........64 4.3 隧道斷面受震之穩定分析.........69 4.3.1 模型幾何介紹.........69 4.3.2 材料參數.........69 4.3.3 動力分析方法.........69 4.3.4 初始條件及邊界條件.........71 4.3.5 分析結果.........72 4.3.6 邊界條件機制之影響分析.........74 4.3.7 地震加載機制分析.........77 4.3.8 地震加速度大小之影響分析.........80 4.4 小結.........89 第五章 處置罐剪力分析.........90 5.1 前言.........90 5.2 模型幾何介紹.........90 5.3 材料參數.........92 5.4 初始條件與邊界條件.........94 5.5 分析結果.........95 第六章 結論與建議.........97 6.1 結論.........97 6.2 建議.........98 參考文獻.........99

    [1] SKB,“Pressure tests of two KBS-3 canister mock-ups”,TR-05-18, 2005.
    [2] SKB,“Design analysis report for the canister”,TR-10-28, April 2010.
    [3] Abaqus Documentation,“Abaqus Theory Manual”取自http://cresearcher-pc:2080/v6.10/books/stm/default.htm
    [4] 台灣電力公司，「用過核子燃料最終處置計畫潛在處置母岩特性調查與評估階段我國用過核子燃料最終處置技術可行性評估報告技術支援報告(2)處置設計與工程技術」，106年12月。
    [5] 台灣電力公司，「用過核子燃料最終處置計畫潛在處置母岩特性調查與評估階段－ 106 年度成果報告 (修訂二版)」，107年5月。
    [6] 核能發電後端營運基金管理會，“Nuclear Fuel Final Disposal Information”取自www.nbef.org.tw/downloads/file/NuclearFuelFinalDisposalInformation.docx
    [7] SKB,“Strategy for thermal dimensioning of the final repository for spent nuclear fuel”,R-09-04, December 2009
    [8] SKB,“Thermal site descriptive model. A strategy for the model development during site investigations - version 2”,R-07-42, September 2007
    [9] SKB,“Framework programme for detailed characterisation in connection with construction and operation of a final repository for spent nuclear fuel”,R-11-14, October 2010
    [10] SKB,“Thermal properties. Site descriptive modelling Forsmark - stage 2.2”,R-07-47, September 2007.
    [11] DE GRUYTER,“Inverse determination of spatially varyingmaterial coecients in solid objects”,March 2016
    [12] Elsevier,“A two-dimensional inverse problem in imaging the thermal conductivity of a non-homogeneous medium”, November 2000
    [13] Inverse problems in science and engineering,“Determination of thermal conductivity of inhomogeneous orthotropic materials from temperature measurements”, December 2018
    [14] SKB,“Probabilistic analysis and material characterisation of canister insert for spent nuclear fuel. Summary report”,TR-05-17, November 2005
    [15] European Commission,“Fracture Properties of Ductile Cast Iron used for Thick-Walled Components”, December 2005
    [16] SKB,“Probabilistic analysis of canister inserts for spent nuclear fuel”,TR-05-19, October 2005.
    [17] Journal of Materials Engineering and Performance,“Tensile, Compression and Fracture Properties of Thick-Walled Ductile Cast Iron Components”, January 2007
    [18] SKB,“Design analysis report for the canister”,TR-10-28, April 2010
    [19] SKB,“Modelling and analysis of canister and buffer for earthquake induced rock shear and glacial load”,TR-10-34August 2010

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