跳到主要內容

臺灣博碩士論文加值系統

(18.97.14.87) 您好!臺灣時間:2025/02/12 10:16
字體大小: 字級放大   字級縮小   預設字形  
回查詢結果 :::

詳目顯示

: 
twitterline
研究生:黃憲章
研究生(外文):Sian Jhang Huang
論文名稱:用過核燃料護套封箱期間熱應力作用之劣化分析
論文名稱(外文):Failure Analysis of Spent fuel Zirconium Cladding during Storing
指導教授:趙振綱
指導教授(外文):Ching-Kong Chao
學位類別:碩士
校院名稱:國立臺灣科技大學
系所名稱:機械工程系
學門:工程學門
學類:機械工程學類
論文種類:學術論文
論文出版年:2006
畢業學年度:94
語文別:中文
論文頁數:91
中文關鍵詞:用過核燃料護套氫化鋯延遲氫化龜裂
外文關鍵詞:spent fuel Zirconium claddinghydridedelay hydried cracking
相關次數:
  • 被引用被引用:1
  • 點閱點閱:147
  • 評分評分:
  • 下載下載:14
  • 收藏至我的研究室書目清單書目收藏:0
本研究主要在探討用過核燃料護套於封箱期間之劣化破壞分析。對於用過核燃料護套之處置,目前有三個處理階段:初步處理(水槽冷卻)、中期處理(乾式貯存)、最終處理(深層掩埋)。但目前國內處理階段只到達乾式中期貯存部分,所以乾式中期貯存就成為現階段最重要的部分。用過核燃料護套在水槽冷卻後到乾式貯存兩個階段中,需經過3個工作天(約72小時)的封箱過程,而本研究就是進行這期間護套劣化分析。
本研究利用有限元素軟體ANSYS進行護套於封箱期間之劣化分析,在模型方面則建立不同裂縫長度、不同裂縫位置、不同排列方位之氫化鋯及裂縫長入與未長入氫化鋯之幾何模型,再根據美國ISG-11導則、護套於正常情況與事故情況三組條件進行有限元素之分析。
經由ANSYS分析後,從三組條件之分析結果檔中找出各個模型之應力強度因子 值,並作三組條件情況下結果比較,說明用過核燃料護套在封箱期間之劣化機制現象及三組條件情況下之差異性,以建立護套之劣化機制與完整的評估數據。
This study focuses on the failure analysis of the spent fuel claddings during the stage between initial disposal and interim dry storage. For the spent fuel claddings, there are three disposals including initial disposal (cooling in sink), interim dry storage and final disposal (deep burying). But up to now, only the disposal with interim dry storage is considered in Taiwan. In general, disposing the spent fuel claddings needs three operate-day (about 72 hours) to store between initial disposal and interim dry storage.
Our purpose in the present study is to perform the degradation analysis of the spent fuel cladding in 72 hours between initial disposal and interim dry storage. A finite element software, ANSYS, is used to analyze the spent fuel claddings by considering the factors such as initial crack lengths, crack locations, hydride orientation, grow into hydride and ungrow into hydride. Beside, three different working conditions are also considered in this study including ISG-11 regulation, claddings at normal condition and claddings at accident condition.
The stress intensity factor is evaluated for these three working conditions which is used as a failure criterion in the present study. This study has established a reliable cladding integrity evaluation for the spent fuel claddings during the stage between initial disposal and interim dry storage.
中文摘要
英文摘要
致謝
目錄
圖表目錄
第一章 緒論
1-1 前言
1-2 研究動機與目的
1-3 文獻回顧
1-4 研究方法
1-5 章節提要
第二章 理論基礎
2-1 應力強度因子
2-2 彈性材料熱應力
2-3 裂縫網格之有限元素法
第三章 有限元素分析
3-1 有限元素法
3-2 前處理
3-3 求解
3-4 後處理
第四章 分析結果與討論
4-1 封箱期間之破壞劣化分析
4-1-1 以ISG-11導則為條件之分析結果
4-1-2 以護套於正常情況為條件之分析結果
4-1-3 以護套於事故情況為條件之分析結果
4-2 ISG-11導則、護套於正常情況與事故情況之分析結果比較
第五章 結論與未來展望
5-1 結論
5-2 未來展望
參考文獻
作者簡介
1.K. A. Gruss, C. L. Brown and M. W. Hodges, “U. S. Nuclear Regulatory Commission Acceptance Criteria and Cladding Considerations for the Dry Storage and Transportation of Spent Fuel,” Proceedings of TopFuel 2003, Würzburg Germany, March 16-19 2003.
2.W. Goll, A. C. Leger and K. McCoy, “Spent Fuel Behavior under Dry Storage Conditions,” ibid.
3.R. Limon, C. Cappelaere, T. Bredel and P. Bouffioux, “A Formulation of the Spent Fuel Cladding Creep Behaviour for Long Term Storage,” Proceedings of the 2000 International Topical Meeting on Light Water Reactor Fuel Performance, Park City, Utah, USA, April 10-13, 2000.
4. R L. Yang, “Meeting The Challenge of Managing Nuclear Fuel in a competitive environment,” Proc. of International Topical Meeting on LWR Fuel Performance, Porland, Oregon(1997).
5. S.-Q. Shi, “Diffusion-controlled hydride growth near crack tip in Zirconium under temperature transients,” J. Nucl. Mat. 275, pp.318-323(1999).
6. Young Suk Kim, “Precipitation of reoriented hydrides and textural change of -Zirconium grains during delayed hydride cracking of Zr-2.5% Nb pressure tube,” J. Nucl. Mat.297, pp.292-302(2001).
7. H. S. Rosenbaun, J. H. Davies and J.Q. Don, “Interaction of Iodine with Zircaloy-2,” Geap-51005(1966).
8. C. J. Simpson and C. E. Ells, “Delayed Hydrogen Embrittlement in Zr-2.5%,” J. Nucl. Mat. 52, pp.289-295(1974).
9. C. E. Coleman and J. F. R. Ambler, “Delayed Hydrogen Cracking in Zr-2.5% Nb Alloy,” Rev. Coating and Corrosion 3:105(1979).
10. S.-Q. Shi, ”Diffusion-Controlled Hydride Growth Near Crack Tip in Zirconium under Temperature Transients,” J. Nucl. Mat. 275, pp.318-323(1999).
11. D. R. Metzger, Ontario Hydro Technologies Report, No.91-102K, (1991).
12. J. Lufrano, P. Sofronis, H.K. Birnbaun, J. Mech. 19 (1984).
13. Y. S. Kim, Y. Perlovich, “precipitation of reoriented hydrides and textural change of -Zirconium grains during DHC of Zr-2.5% Nb pressure tube,” J. Nucl. Mat. 297, pp.292-302 (2001).
14. M. Kuroda, S. Yamanaka, D. Setoyama, “Tensile test of hydrided Zircaloy,” J. Nucl. Mat. 330-332 (2002) 404-407.
15. M. Kuroda, S. Yamanaka, F. Nagase, H. Uetsuka, Nucl. Eng. Des.
203 (2001) 185.
16. M. Kuroda, K. Yoshioka, S. Yamanaka, H. Anada, F. Nagase, H.
Uetsuka, J. Nucl. Sci. Technol 37 (2000) 670.
17. S. Yamanaka, M. Kuroda, D. Setoyama, “Analysis of The Fracture Behavior of Hydrided Cladding Tube at Elevated Temperature by Fracture Mechanics,” J. Nucl. Mat. 330-332 (2002) 400-403.
18. M. Kuroda, K. Yoshioka, S. Yamanaka, H. Anada, F. Nagase, H.
Uetsuka, J. Nucl. Sci. Technol 37 (2000) 670.
19. M. Kuroda, S. Yamanaka, F. Nagase, H. Uetsuka, Nucl. Eng. Des.
203 (2001) 185.
20. A. Tasooji, et.al., “Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effect and Dry Storage Spent Fuel Behavior,” American Society for Testing and Material, pp.595-626 (1984).
21. “Cladding Consideration for the Transportation and Storage of Spent fuel,“ Interim Staff Guideance-11, Revision 3, Spent Fuel Project Office, Nuclear Regulatory Commission, November 17, 2003.
QRCODE
 
 
 
 
 
                                                                                                                                                                                                                                                                                                                                                                                                               
第一頁 上一頁 下一頁 最後一頁 top