| 研究生: |
徐維祥 Wei-Hsiang Hsu |
|---|---|
| 論文名稱: |
用過核子燃料廢料罐之峰值溫度熱傳分析及圍壓暨位移影響參數分析 |
| 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: | 2024 |
| 畢業學年度: | 112 |
| 語文別: | 中文 |
| 論文頁數: | 80 |
| 中文關鍵詞: | 用過核子燃料 、深層地質處置場 、廢料罐體之熱傳分析 、熱載重 、處置罐位移 |
| 外文關鍵詞: | used nuclear fuel, deep geological disposal facility, thermal analysis of waste canisters, disposal canisters, seismic displacement |
| 相關次數: | 點閱:11 下載:0 |
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因用過核子燃料具有三大特性,分別是長半衰期、高放射性及大衰變熱,須審慎思考如何減少其威脅,經國際間經長期評估兼具安全及效率的處置方式為深層地質處置(deep geologic disposal)。
在建置處置場前,為提升其安全性,需進行相關數值模擬分析,本研究使用有限元素分析軟體ABAQUS進行,並探討及觀察廢料罐罐體之熱傳現象、圍壓及位移效應。
本文第四章首先參考國際計畫DECOVALEX文獻所提供的模型條件,使用代表體積單元方法建具相同效力模型,求得罐處置罐最高溫度並與文獻平行驗證,並針對前一步的溫度結果進行熱載重做參數分析。
此外,第五章針對SKB發表文獻進行處置罐的圍壓數值模擬分析,探討罐體受圍壓情形,並與其實驗結果進行平行驗證。並進一步針對加入地震可能產生之位移觀察其分析結果再加以討論。
Due to the three main characteristics of spent nuclear fuel—long half-life, high radioactivity, and significant decay heat—it is crucial to carefully consider how to mitigate its threats. After long-term international assessments, deep geologic disposal has been identified as a method that ensures both safety and efficiency.
Before establishing disposal sites, it is essential to enhance safety through relevant numerical simulations. This study employs the finite element analysis software ABAQUS to investigate and observe the thermal transfer phenomena, confining pressure, and displacement effects on the waste canisters.
In Chapter 4, the study first references the model conditions provided by the international DECOVALEX project literature. Using the Representative Volume Element (RVE) method, a model with equivalent effectiveness is constructed to determine the maximum temperature of the disposal canister, which is then verified against the literature. Subsequently, a parametric analysis is conducted on the thermal load based on the previous temperature results.
Additionally, Chapter 5 conducts a numerical simulation analysis of the confining pressure on the disposal canisters, referencing the literature published by SKB. The study examines the canister's response to confining pressure and verifies the results against experimental data. Further, the study incorporates potential displacements caused by seismic activity, analyzes the results, and discusses the findings.
[1] Posiva and SKB,“Temperatures inside SKB and Posiva type disposal canisters for spent fuel”, Posiva SKB Report 12, December 2020.
[2] SKB,“Pressure tests of two KBS-3 canister mock-ups”,TR-05-18, 2005.
[3] 台灣電力公司,「用過用過核子燃料最終處置計畫候選場址評選與核定階段 111年度工作計畫 (修訂二版) 」,108年12月。
[4] NUMO,"高レベル放射性廃棄物地層処分の技術と安全性",2004
[5] SOLIDWORKS說明,“熱對流係數” ,取自http://help.solidworks.com/2010/chinese/SolidWorks/cworks/legacyhelp/simulation/AnalysisBackground/ThermalAnalysis/Convection_Topics/Convection_Heat_Coefficient.htm。
[6] 謝馨輝,「核廢料地下處置之熱傳導及初步熱應變分析」,國立中央大學,碩士論文,2003。
[7] 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)」,106年12月。
[8] SKB, “Water saturation phase of the buffer and backfill in the KBS-3V concept” , TR-06-14, August 2006.
[9] 徐宇儁, 「用過核子燃料最終處置場之處置罐剪力分析及熱誘發地震分析」,國立中央大學,碩士論文,2010。