| 研究生: |
陳志霖 Chih-Ling Chen |
|---|---|
| 論文名稱: |
放射性廢料處置場緩衝材料之力學性質 Mechanics of Buffer Materials in Nuclear Wastedisposal |
| 指導教授: |
黃偉慶
Wei-Hsing Huang |
| 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 |
| 畢業學年度: | 88 |
| 語文別: | 中文 |
| 論文頁數: | 99 |
| 中文關鍵詞: | 緩衝材料 、靜態壓實 、雙曲線模式 、核廢料處置場 、三軸試驗 、力學性質 |
| 外文關鍵詞: | buffer material, static compaction, hyperbolic model, nuclear |
| 相關次數: | 點閱:10 下載:0 |
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本文主旨在於以三軸試驗探討膨潤土–碎石之緩衝材料力學性
質,並建立理論模式來預測緩衝材料之應力–應變曲線。
為提高試體之均勻性,本文使用分層靜態壓實法來製作試體,以
探討膨潤土乾密度、碎石體積百分比在不同圍壓下對緩衝材料之力學
性質影響。由試驗結果顯示,分層靜態壓實法能有效提升試體之均勻
性。就核廢料處置場中緩衝材料之力學性質而言,提高膨潤土乾密度、
增加碎石含量體積百分比以及加大圍壓皆能提升緩衝材料之力學強
度;但在提高膨潤土乾密度及增加碎石含量體積百分比的同時,緩衝
材料的應力–應變關係也逐漸趨於脆性破壞的形態,這會降低緩衝材
本文另一重點在於利用複合材料力學中微觀力學模式配合雙曲線
模式以及靜態壓實試驗,來預測不同乾密度與不同膨潤土體積比的緩
衝材料在不同圍壓下的力學性質;預測結果與本文試驗結果相較,顯示兩者相當吻合。
buffer in order to find out it’s mechanical properties and built up predicted
model of it’s mechanical performance. Bentonite was mixed with different
volume fraction of crushed granite, and specimens were statically compacted
to many dry density. To getting uniform specimen, each layer were
compacted statically until the specimen had been made. Results indicate that
having high dry density, mixed with more crushed granite content, and in
high confining pressure will get good shear strength, but it’s energy capacity
will be lost at the same time.
大學土木工程研究所,台南,(1992)。
2. 卓智聰,「放射性廢料處置場緩衝材料之物理特性及配方研
究」,碩士論文,國立中央大學土木系,中壢,(1999)。
3. 陳衛里,「用過核燃料直接處理」,核能季刊,第三期,第3-
4. 張瑟稀,從雅卡山經驗談放射性廢料最終處置,核研季刊,
第二十七期,第77-81 頁,(1998)。
5. 葉有財,「日本放射性廢料之永久處理」,核能天地,10 月號,
第26-27 頁,(1994)。
6. 葉佐仁,「放射性廢料處置場回填材料之物理特性及配方研
究」,碩士論文,國立中央大學土木系,中壢,(1998)。
7. 劉尚志、林鴻旭、焦自強、張璞,「高放射性廢料終極處置—
工程障壁之探討」,原子能委員會核能彙刊,第二十五卷,
第四期,第20~37 頁,民國七十八年八月。
8. Radhakrishna, H. S., “Thermal Properties of Clay-Based Buffer
Materials for a Nuclear Fuel Waste Disposal Vault,” AECL
Report, Pinawa, Canada, (1984).
9. Borgesson, L., O. Karnland, and L. E. Johannesson, “Modelling
of the Physical Behaviour of Clay Barriers Close to Water
Saturation,” Engineering Geology, Vol. 41, pp. 127-144(1994).
10. Borgesson, L., A. Fredrikson, and L. E. Johannesson, “Heat
Conductivity of Buffer Materials,” SKB Report, Lund, Sweden,
(1994).
11. Branley, W., J. Graham,G. X. Tang, and D. Dixon, “Influence of
Pressure, Saturation, and Temperature on Behavior of
Unsaturated Sand-Bentonite,” Can. Geotech. J. Vol. 35, pp. 194-
205(1998).
12. Geneste, P., M. Raynal, R. Atabek, M. Dardaine, and J. Oliver,
“Characterization of a French Clay Barrier and Outline of the
Experimental Programme,” Engineering Geology, Vol. 28, pp.
443-454(1990).
13. Gera, F., T. Hueckel, and A. Peano, “Critical Issues in Modelling
the Long-Term Hydro-thermo-mechanical Performance of
Natural Clay Barriers,” Engineering Geology, Vol. 41, pp. 17-
33(1995).
14. Gray, M. N., S. C. H. Cheung, and D. A. Dixon, ”The Influence
of Sand Content on Swelling Pressure and Structure Developed
in Statically Compacted Na-Bentonite,” Atomic Energy of
Canada Limited, Report AECL-7825, Pinawa, Man., (1984).
15. Komine, H., and N. Ogata, “Experimental Study on Swelling
Characteristics of Compacted Bentonite,” Can. Geotech. J. Vol.
31, pp. 478-490 (1994).
16. Nakashima, H., T. Ishii, and T. Nagasawa, “Method of Designing
Bentonite/Sand Mixture to Achieve the Target Permeability,” et
al. Mat. Res. Soc. Symp. Proc., Vol. 353, pp. 247-252 (1995).
17. OCRWM, “Viability Assessment of a Repository at Yucca
Mountain,” USDE, North Las Vegas, U. S., (1998).
18. Pigford, T. H., “The Engineered Barrier System:Performance
Issues, ” Mat. Res. Soc. Symp. Proc., Vol. 294, pp. 657-662
(1993).
19. Radhakrishna, H. S., “Thermal Properties of Clay-Based Buffer
Materials for a Nuclear Fuel Waste Disposal Vault,” AECL
Report, Pinawa, Canada, (1984).
20. Radhakrishna, H. S., and H. T. Chan, “Thermal and Physical
Properties of Candidate Buffer-Backfill Materials for a Nuclear
Fuel Waste Disposal Vault,” Can. Geotech. J. Vol. 26, pp. 629-
639 (1989).
21. Wardrop, W. L., and Associates Ltd., “Buffer and Backfilling
Systems for a Nuclear Waste Disposal Vault,” AECL Report,
Pinawa, Canada, (1985).
22. INER, 經濟部核能研究所年度簡報資料,未出版(1999)。
23. 清蔚園,「什麼是放射性廢料?」,
http://vm.nthu.edu.tw/science/shows/nuwaste/index.html,
2000。
24. OCRWM, http://www.rw.doe.gov/homejava/homejava.htm,
2000.
25. SKB, http://www.skb.se/engelska/skb/index.html, 2000.