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Student Number 88322056
Author De-Chan Wu(鄔德傳)
Author's Email Address No Public.
Statistics This thesis had been viewed 1251 times. Download 812 times.
Department Civil Engineering
Year 2000
Semester 2
Degree Master
Type of Document Master's Thesis
Language zh-TW.Big5 Chinese
Title none
Date of Defense 2001-07-12
Page Count 102
Keyword
  • buffer material
  • waste containers
  • Abstract Radioactive wastes are required to be isolated from the environment to prevent possible contamination. The disposal concept presently being considered is “deep geological disposal ”. In an underground disposal site, the radioactive wastes are encapsulated in containers surrounded by a buffer material and excavation backfilled.
    The study aims at determining the proper time interval to calculate the thermal conductivity of the buffer material, and using the actual heat conductivity of the sample known to evaluate the influence of different factors. The aim of these calculations was to develop the most appropriate test and evaluation method.
    Table of Content 中 文 摘 要I
    英 文 摘 要II
    誌 謝III
    目 錄IV
    圖 目 錄VII
    表 目 錄X
    第一章 緒論1
    1.1前言1
    1.2研究動機與目的2
    1.3研究方法4
    1.4論文內容5
    第二章 文獻回顧7
    2.1前言7
    2.2放射性廢料處置之相關研究7
    2.3熱傳性質之相關研究9
    2.4緩衝材料熱傳導係數試驗10
    第三章 熱力學分析理論與數值模擬分析方法16
    3.1前言16
    3.2熱力學分析理論17
    3.2.1熱傳導17
    3.2.2熱對流19
    3.3數值分析理論20
    3.3.1有限元素20
    3.3.2利用軸對稱方法進行數值模擬23
    3.4緩衝材料熱傳導係數試驗之介紹24
    3.5分析方法25
    3.5.1使用程式之介紹25
    3.5.2接觸熱阻之介紹26
    3.5.3數值模擬方法27
    第四章 分析結果與討論34
    4.1前言34
    4.2實驗驗證35
    4.2.1網格收斂之確認35
    4.2.2材料性質之探討37
    4.2.2.1熱源比熱探討37
    4.2.2.2熱源密度探討38
    4.2.2.3熱源熱傳導係數探討39
    4.2.2.4熱源選用材料探討39
    4.2.3過渡區介面之探討40
    4.2.4熱傳導係數計算方法之探討43
    4.2.5實驗之驗證45
    4.3實驗參數之理論模擬分析47
    4.3.1土樣試體外緣邊界情形之分析47
    4.3.2過渡區介面熱傳導係數之分析48
    4.3.3提供熱能之分析49
    4.3.4土樣熱傳導係數之分析49
    4.4案例分析50
    第五章 結論與建議84
    5.1結論84
    5.2建議85
    參考文獻86
    Reference 【1】Selvadurai, A.P.S., and Nguyen, T.S., “Scoping analyses of the coupled thermal-hydrological-mechanical behavior of the rock mass around a nuclear fuel waste repository,” Engineering Geology, Vol.47, pp.379-400, 1996.
    【2】Farouki, O.T., “Thermal Properties of Soils,” Trans Tech Publications, 1986.
    【3】Woodside, W., and Messmer, J.M., “Thermal conductivity of porous media,” Journal of Applied Physics, vol. 32, No. 9, 1961.
    【4】Kahr, G., and Muller-von Moos, m., "Warmeleitfahigkeit von Bentonit Mx80 und von Montigel nach der Heizdrahtmethode,” NAGRA Technischer Bericht 82-06, 1982.
    【5】Beziat, A., Dardaine, M. and Gabis, V., “Effect of compaction pressure and water content on the thermal conductivity of some natural clays,” Clays & Clays Minerals 36 (5), 1988.
    【6】Knutsson, S., “On the thermal conductivity and thermal diffusivity of highly compacted bentonite,” SKB Technical Report 83-72, 1983.
    【7】Radhakrishna, H. S., Chan, H. T., Crawford, A. M., and Lau, K. C., “Thermal and Physical Properties of Candidate Buffer-Backfill Material for a Nuclear Fuel Waste Disposal Vault,” Canadian Geotechnical Journal, Vol.26, pp.629-639, 1989.
    參考文獻
    【1】Selvadurai, A.P.S., and Nguyen, T.S., “Scoping analyses of the coupled thermal-hydrological-mechanical behavior of the rock mass around a nuclear fuel waste repository,” Engineering Geology, Vol.47, pp.379-400, 1996.
    【2】Farouki, O.T., “Thermal Properties of Soils,” Trans Tech Publications, 1986.
    【3】Woodside, W., and Messmer, J.M., “Thermal conductivity of porous media,” Journal of Applied Physics, vol. 32, No. 9, 1961.
    【4】Kahr, G., and Muller-von Moos, m., "Warmeleitfahigkeit von Bentonit Mx80 und von Montigel nach der Heizdrahtmethode,” NAGRA Technischer Bericht 82-06, 1982.
    【5】Beziat, A., Dardaine, M. and Gabis, V., “Effect of compaction pressure and water content on the thermal conductivity of some natural clays,” Clays & Clays Minerals 36 (5), 1988.
    【6】Knutsson, S., “On the thermal conductivity and thermal diffusivity of highly compacted bentonite,” SKB Technical Report 83-72, 1983.
    【7】Radhakrishna, H. S., Chan, H. T., Crawford, A. M., and Lau, K. C., “Thermal and Physical Properties of Candidate Buffer-Backfill Material for a Nuclear Fuel Waste Disposal Vault,” Canadian Geotechnical Journal, Vol.26, pp.629-639, 1989.
    Advisor
  • Jui-Hung Chang(張瑞宏)
  • Files
  • 88322056.pdf
  • approve immediately
    Date of Submission 2001-07-12

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