用過核子燃料最終處置場之間隙熱效應、KBS-3H熱傳導參數影響分析及處置罐焊接熱致應力參數影響分析

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Please use this identifier to cite or link to this item: http://ir.lib.ncu.edu.tw/handle/987654321/91760

Title:	用過核子燃料最終處置場之間隙熱效應、KBS-3H熱傳導參數影響分析及處置罐焊接熱致應力參數影響分析
Authors:	陳丁豪;Chen, Ting-Hao
Contributors:	土木工程學系
Keywords:	用過核子燃料;深層地質處置場;KBS-3H;現地化模型;處置罐焊接;熱-水力耦合;熱-力耦合;spent nuclear fuel;deep geological repository;KBS-3H;on-site localization model;disposal canister welding;thermal-hydraulic coupled;thermal-stress coupled
Date:	2023-07-12
Issue Date:	2024-09-19 14:12:43 (UTC+8)
Publisher:	國立中央大學
Abstract:	核能發電後所產生的用過核子燃料具有長半衰期、高放射性及高衰變熱等特性，國際間經過多年研究後認為，最有效的最終處置方案為深層地質處置法。在建造深層地質處置場之前，為了確保其安全性，事前評估工作就顯得非常重要，必須進行一系列相關之數值模擬分析。本研究使用有限元素軟體ABAQUS進行相關之數值模擬分析，探討溫度場、飽和度場、應力場之物理場效應。本研究之主題一參考文獻，了解空氣與含雜質間隙的產生是否會對處置部件產生熱行為之交互影響，並進一步模擬不同材料之間隙對於整個處置場域之溫度場影響分析。主題二則是參考芬蘭POSIVA文獻，針對SKB和Posiva於2002年聯合探究之水平處置法KBS-3H進行相關之現地化之溫度場及飽和度場數值模擬，並針對緩衝材料之熱傳導係數進行參數影響分析。最後，主題三研究最終處置法中的處置罐，在尚未放入用過核子燃料前執行環向焊接工序之相關數值平行驗證工作，並進行軸向焊接之溫度場以及應力場的相關參數分析。 ;After many years of international research, it is widely recognized that the most effective final disposal method for spent nuclear fuel, which possesses long half-life, high radioactivity, and high decay heat, is deep geological disposal. Before constructing a deep geological repository, it is crucial to conduct pre-assessment work to ensure its safety. This involves a series of numerical simulation analyses. In this study, the finite element software ABAQUS is used for relevant numerical simulations to investigate the thermal field, saturation field, and stress field. The first theme of this study refers to the relevant research. It establishes the concept of air or impurity-filled gaps to understand whether the generation of gaps would have interactive effects on the thermal behavior of disposal components. Furthermore, it simulates the influence analysis of different material gaps on the temperature field in the entire disposal site. The second theme refers to the Finnish literature on the KBS-3H horizontal disposal method, which was jointly explored by SKB and Posiva in 2002. It conducts numerical simulations of the temperature field and saturation field for on-site model and performs a parameter analysis on the thermal conductivity of the buffer material. Lastly, the third theme focuses on the disposal canisters in the final disposal method. It carries out parallel verification work for the circumferential welding process before loading the spent nuclear fuel, and conducts parameter analysis of the temperature field and stress field for the axial welding.
Appears in Collections:	[Graduate Institute of Civil Engineering] Electronic Thesis & Dissertation

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