用過核子燃料最終處置場之母岩破裂帶影響效應分析及現地實驗數值模擬

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題名:	用過核子燃料最終處置場之母岩破裂帶影響效應分析及現地實驗數值模擬
作者:	張道盛;Chang, Tao-Sheng
貢獻者:	土木工程學系
關鍵詞:	用過核子燃料;深層地質處置場;膨潤土;破裂帶;Spent Nuclear Fuel;Deep Geological Repository;bentonite;fracture
日期:	2019-07-29
上傳時間:	2019-09-03 12:13:14 (UTC+8)
出版者:	國立中央大學
摘要:	用過核子燃料具有高衰變熱以及高放射性的特性，對於其之有效安全處理方法，國際間經多年的研究認為，深層地質處置是較為恰當的最終處置方法。為了確保處置場的安全性，事前的分析極為關鍵。衰變熱產生的高溫可能使處置孔內部材料產生質變，致使材料無法發揮隔離功效，此外，當緩衝材料達到完全飽和後，用過核子燃料與地下水接觸時，導致放射性核種從處置罐中釋出。本研究主要圍繞在處置場的溫度及再飽和時間等問題進行深入探討，全文使用有限元素軟體ABAQUS分析模擬。首先，處置場中破裂帶的存在，致使地下水可藉由破裂帶於處置場中快速流動，而加速緩衝材料再飽和的時間，本研究參考瑞典核子燃料與廢棄物管理公司(SKB)分析多組案例，且與SKB進行溫度及再飽和時間平行驗證，確認本研究之可靠度，進一步針對熱對流邊界及近場母岩排水進行分析。其次，SKB模擬現地實驗之相關參數，對其數值分析結果進行溫度及再飽和過程平行驗證。在SKB的現地實驗中，使用自由控制的人工加熱器與濾水器來模擬用過核子燃料及周邊地下水的影響，故可藉由其來考驗數值模擬的驗證技術。最後，參考國際合作計畫DECOVALEX文獻的BMT1B工作任務，模擬處置場近場的性能，且與各國團隊的溫度及再飽和時間進行平行驗證，同時，對處置隧道靜置通風冷卻效應進一步的探討。 ;Spent nuclear fuel is high temperature as well as highly radioactive and requires remote handling and shielding. The international consensus is that deep geological repository in a stable host rock deep underground is the most reliable method. In order to ensure the safety of repository, prior analysis is extremely critical. The high temperature generated by the decay heat may deteriorate the material inside the disposal hole, resulting in the material not being able to isolate radionuclides. In addition, when the buffer is fully saturated, Spent Nuclear Fuel in contact with the groundwater causes radionuclides to be released from the canister. This study mainly discusses the time of resaturation and peak temperature of the repository. Each analysis is modelled by the finite element software ABAQUS. First, the existence of fractures in the repository, causing groundwater to flow rapidly through the cracks, accelerating the time of resaturation. In this study, rock fracture has been modelled with different cases. All cases refer to Swedish Nuclear Fuel and Waste Management Company (SKB). Results of temperature and resaturation time have been compared with SKB. Secondly, in the in-situ experiment, artificial heater and filters were used to simulate the effects of spent nuclear fuel and groundwater. The experiment has been modelled temperature and saturation history by SKB. In this study, the model has established the same conditions as SKB for parallel verification. Finally, near field of the repository has been modelled by different research teams in the BMT1B of DECOVALEX III project. In this study, results of this study will be compared with the temperature and the time of resaturation of each team.
顯示於類別:	[土木工程研究所] 博碩士論文

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