| DC 欄位 |
值 |
語言 |
| DC.contributor | 土木工程學系 | zh_TW |
| DC.creator | 徐維祥 | zh_TW |
| DC.creator | Wei-Hsiang Hsu | en_US |
| dc.date.accessioned | 2024-7-26T07:39:07Z | |
| dc.date.available | 2024-7-26T07:39:07Z | |
| dc.date.issued | 2024 | |
| dc.identifier.uri | http://ir.lib.ncu.edu.tw:444/thesis/view_etd.asp?URN=111322034 | |
| dc.contributor.department | 土木工程學系 | zh_TW |
| DC.description | 國立中央大學 | zh_TW |
| DC.description | National Central University | en_US |
| dc.description.abstract | 因用過核子燃料具有三大特性，分別是長半衰期、高放射性及大衰變熱，須審慎思考如何減少其威脅，經國際間經長期評估兼具安全及效率的處置方式為深層地質處置(deep geologic disposal)。
在建置處置場前，為提升其安全性，需進行相關數值模擬分析，本研究使用有限元素分析軟體ABAQUS進行，並探討及觀察廢料罐罐體之熱傳現象、圍壓及位移效應。
本文第四章首先參考國際計畫DECOVALEX文獻所提供的模型條件，使用代表體積單元方法建具相同效力模型，求得罐處置罐最高溫度並與文獻平行驗證，並針對前一步的溫度結果進行熱載重做參數分析。
此外，第五章針對SKB發表文獻進行處置罐的圍壓數值模擬分析，探討罐體受圍壓情形，並與其實驗結果進行平行驗證。並進一步針對加入地震可能產生之位移觀察其分析結果再加以討論。 | zh_TW |
| dc.description.abstract | Due to the three main characteristics of spent nuclear fuel—long half-life, high radioactivity, and significant decay heat—it is crucial to carefully consider how to mitigate its threats. After long-term international assessments, deep geologic disposal has been identified as a method that ensures both safety and efficiency.
Before establishing disposal sites, it is essential to enhance safety through relevant numerical simulations. This study employs the finite element analysis software ABAQUS to investigate and observe the thermal transfer phenomena, confining pressure, and displacement effects on the waste canisters.
In Chapter 4, the study first references the model conditions provided by the international DECOVALEX project literature. Using the Representative Volume Element (RVE) method, a model with equivalent effectiveness is constructed to determine the maximum temperature of the disposal canister, which is then verified against the literature. Subsequently, a parametric analysis is conducted on the thermal load based on the previous temperature results.
Additionally, Chapter 5 conducts a numerical simulation analysis of the confining pressure on the disposal canisters, referencing the literature published by SKB. The study examines the canister′s response to confining pressure and verifies the results against experimental data. Further, the study incorporates potential displacements caused by seismic activity, analyzes the results, and discusses the findings. | en_US |
| DC.subject | 用過核子燃料 | zh_TW |
| DC.subject | 深層地質處置場 | zh_TW |
| DC.subject | 廢料罐體之熱傳分析 | zh_TW |
| DC.subject | 熱載重 | zh_TW |
| DC.subject | 處置罐位移 | zh_TW |
| DC.subject | used nuclear fuel | en_US |
| DC.subject | deep geological disposal facility | en_US |
| DC.subject | thermal analysis of waste canisters | en_US |
| DC.subject | disposal canisters | en_US |
| DC.subject | seismic displacement | en_US |
| DC.title | 用過核子燃料廢料罐之峰值溫度熱傳分析及圍壓暨位移影響參數分析 | zh_TW |
| dc.language.iso | zh-TW | zh-TW |
| DC.type | 博碩士論文 | zh_TW |
| DC.type | thesis | en_US |
| DC.publisher | National Central University | en_US |