放射性廢料處置場緩衝材料之力學性質; Mechanics of Buffer Materials in Nuclear Waste disposal

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Please use this identifier to cite or link to this item: http://ir.lib.ncu.edu.tw/handle/987654321/506

Title:	放射性廢料處置場緩衝材料之力學性質;Mechanics of Buffer Materials in Nuclear Waste disposal
Authors:	陳志霖;Chih-Ling Chen
Contributors:	土木工程研究所
Keywords:	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;buffer material;static compaction;hyperbolic model;nuclear
Date:	2000-07-28
Issue Date:	2009-09-18 17:06:44 (UTC+8)
Publisher:	國立中央大學圖書館
Abstract:	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。 Triaxial compression tests were performed on bentonite-crushed granite 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.
Appears in Collections:	[Graduate Institute of Civil Engineering] Electronic Thesis & Dissertation

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