| DC 欄位 |
值 |
語言 |
| DC.contributor | 土木工程學系 | zh_TW |
| DC.creator | 許正煜 | zh_TW |
| DC.creator | Hsu, Cheng-Yu | en_US |
| dc.date.accessioned | 2022-8-3T07:39:07Z | |
| dc.date.available | 2022-8-3T07:39:07Z | |
| dc.date.issued | 2022 | |
| dc.identifier.uri | http://ir.lib.ncu.edu.tw:444/thesis/view_etd.asp?URN=109322016 | |
| 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 | 本研究以瑞典核子燃料及廢棄物管理公司提出之「深層地質處置」概念為基礎，參考瑞典及國內相關文獻對於處置場尺寸與廢料罐潛在位置分佈之設計，且考慮母岩之熱、力學、熱-力學及水力-力學特性，並以有限元素軟體ABAQUS進行熱-水-力耦合分析。
本研究主題一「處置場遠場之溫度場影響研析」為針對廢料罐處置後放射性核種仍持續釋放之衰變熱來進行研析，首先，進行處置場遠場之熱傳導平行驗證，本文於各觀測線之趨勢及分析結果皆與相關文獻相當接近，溫度脈衝在大約300年後到達地表，在兩處置區域之間與中央設施區域之最大溫度增量明顯較低，約5至10°C (直接通過處置區域處約為25°C），並且發生的時間要晚得多，約發生於1000年後(直接通過處置區域處約為100年附近）。
本研究主題二「處置場遠場之熱應力及地表隆起影響研析」為接續主題一之溫度場分析結果，平行驗證案例於各觀測線之各向應力趨勢及結果皆與文獻相近，並在直接通過處置區域處有最大之應力分析結果。
本研究主題三「處置場遠場之剪切位移及水力傳導度影響研析」為接續主題二之熱應力分析結果，分析時以剪切位移及水力傳導度兩個主題進行研析，首先，本文根據相同裂縫半徑下得出之最大剪切位移，發現垂直處置區域之觀測線的裂縫更加穩定；最後，當正向應力降低時，水力傳導度可能會隨之增加，因此最大的潛在不穩定性裂縫出現在與非處置區域垂直的位置。 | zh_TW |
| dc.description.abstract | This research is based on the “deep geological disposal” proposed by the Swedish Nuclear Fuel and Waste Management Company (SKB). On the basis of this concept, thermal, mechanical, thermo-mechanical, hydro-mechanical properties of the rock along with the layouts of the repository size and potential canister locations are analyzed. The following three topics are examined with the thermo-hydro-mechanical coupling analysis performed by the finite element software ABAQUS.
The first topic, The Influence of the Temperature Distribution in the Repository Far Field, focuses on the heat released by reason of radionuclide delay after canisters are deposited. The parallel verification of the heat transfer in the repository far field showed the temperature pulse reached the ground surface after about 300 years. Moreover, the maximum temperature increased between the two deposition areas and the central area was significantly lower (around 5-10°C) than it was directly through the deposition area (about 25°C). In addition, it occurred much later (about 1,000 years later) compared to it did directly through the deposition area (around 100 years later). These trends are consistent with the previous literature.
Following the results of temperature field analysis from Topic 1, the next topic is The Influence of Thermally-Induced Stresses in Repository Far Field and Heave of the Ground Surface. In line with past studies, the results showed the maximum stresses were found directly through the deposition area.
The final topic is The Influence of Shear Displacement and Hydraulic Transmissivity in Repository Far Field, continuing thermally-induced stress study from Topic 2.The analysis includes the shear displacement and hydraulic transmissivity. Based on the maximum shear displacement calculated under the same fracture radius, fractures perpendicular to the scanlines of the deposition areas were more stable. Furthermore, the hydraulic transmissivity increased as the normal stress decreased. Therefore, the maximum potential unstable fractures appeared in the deposition areas non-perpendicular to fractures. | en_US |
| DC.subject | 用過核子燃料 | zh_TW |
| DC.subject | 深層地質處置場遠場 | zh_TW |
| DC.subject | 耦合熱-水-力學分析 | zh_TW |
| DC.subject | spent fuel | en_US |
| DC.subject | deep geologic repository far field | en_US |
| DC.subject | thermo-hydro-mechanical coupling analysis | en_US |
| DC.title | 用過核子燃料最終處置場遠場之熱、力學、熱-力學及水力-力學耦合分析 | 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 |