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研究生： 莊棣守
Chuang, Di-Shou
論文名稱： 用過核子燃料乾式貯存設施場址與混凝土護箱受震分析
Independent Spent Fuel Storage Installation (ISFSI) Design Ground Motion and Concrete Casks Stability Analysis at the Pad
指導教授： 朱聖浩
Ju, Shen-Haw
學位類別： 碩士
Master
系所名稱： 工學院 - 土木工程學系碩士在職專班
Department of Civil Engineering (on the job class)
論文出版年： 2017
畢業學年度： 105
語文別： 英文
論文頁數： 140
中文關鍵詞： 獨立用過核燃料乾式貯存設施 、標準審查計畫 、土壤結構互制分析 、ANSYS LS-DYNA程式
外文關鍵詞： ISFSI, SRP, SSI, ANSYS LS-DYNA
相關次數： 點閱：104  下載：0 
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    • 隨著國內核電廠如金山核電廠及國聖核電廠，逐漸面臨用過核燃料池滿，沒有空間可容納由反應爐退出之用過核燃料棒的問題，將如何處理這些用過核燃料棒，已經是無法避免的課題。未來，即使是核電廠除役，也仍需面臨如何處理退出在燃料池內，幾萬根用過核燃料棒的問題。
    獨立用過核燃料乾式貯存設施的設計規範是依照美國核能管理委員會（NRC），國際原子能總署（IAEA）等之法規設計，如NUREG 0800 SRP（標準審查計畫），NUREG 1536（乾式貯存護箱系統標準審查計畫），10CFR72（用過核燃料、高放射性廢棄物之許可及反應爐超過C等級之相關廢棄物存放要求），ACI 349（美國核安全相關混凝土結構規範）等進行設計。本論文是以國內核電廠之規畫處理用過核燃料乾式貯存設施的實際經驗，考量基地場址條件、SSI（土壤結構互制分析）效應、山腳斷層新事證及地質改良、超越設計基準之地震力( RLE）等相關設計地震議題，以分析VCC（Vertical Concrete Cask）在混凝土基座(PAD)的穩定性。本文以有限元素分析軟體ANSYS Workbench LS-DYNA模擬VCC在混凝土基座上的結構行為及分析。冀望本文有助於將來核電廠除役時，規劃處理用過核子燃料之參考。

    With the domestic nuclear power plants, the Chinshan nuclear power plant and the Kuosheng nuclear power plant gradually faced with spent nuclear fuel pools full, the fuel pool has no room to accommodate the spent nuclear fuels, how to deal with these spent nuclear fuels, has become unable to avoid the problem. In the future, even if the nuclear power plant decommissioning, how to deal with tens of thousands of spent nuclear fuels, still have to pay attention to the problem.
    The Independent spent fuel storage installation (ISFSI) design specifications is based on the Nuclear Regulatory Commission (NRC), the International Atomic Energy Agency (IAEA) codes, such as NUREG 0800 SRP (STANDARD REVIEW PLAN), NUREG 1536 (Standard Review Plan for Dry Cask Storage Systems), 10CFR72 (LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE), ACI 349 (Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary) and so on. This thesis is based on the actual experience of nuclear fuel dry storage facilities in domestic nuclear plant, considering the relevant seismic topics such as site conditions, SSI (soil-structure coordination analyses) effect, the Shanchiao fault and site improvement, Review Level Earthquake (RLE) etc. to analysis the stability of VCC (Vertical Concrete Cask) and concrete PAD. Computer code ANSYS Workbench LS-DYNA is used to simulate the structural behavior and analysis of the concrete pad and VCC. It is expected to be helpful as a reference for future nuclear power plant decommissioning.

    CHAPTER 1. INTRODUCTION 1 1.1 The status of ISFSI in the world 1 1.2 The status of dry storage facilities in Taiwan 2 1.3 Earthquake investigation and seismic design analysis : 3 1.3.1 Geological And Seismic Investigation 3 1.3.2 Specification for seismic design analysis： 4 1.4 Codes and standards 6 1.4.1 General 6 1.4.2 Applicable codes and standards 6 1.5 Acronyms and Abbreviations List 14 CHAPTER 2. ANALYSIS OF SEISMIC RESPONSE 16 2.1 Development of Acceleration Time Histories 16 2.1.1 Code Requirement 16 2.1.2 Purpose and Scope 17 2.1.3 Method of Analysis 17 2.1.4 Design Input 18 2.1.5 Analysis 19 2.2 Development of Strain Compatible Soil Properties 28 2.2.1 Code Requirement 28 2.2.2 Purpose and Scope 32 2.2.3 Method of Analysis 32 2.2.4 Design Input 33 2.2.5 Analysis 36 2.3 Soil-Structure Interaction (SSI) Analysis for the ISFSI Pad 52 2.3.1 Synopsis of Results 52 2.3.2 Purpose and Scope 52 2.3.3 Method of Analysis 52 2.3.4 Design Input 53 2.3.5 Assumptions 64 2.3.6 Analysis 65 2.3.7 Soil improvement 87 2.3.8 Review Level Earthquake (RLE) Evaluation 98 2.3.9 Conclusions 103 CHAPTER 3. VCC SATBILITY ANANLYSIS AT THE PAD 104 3.1 VCC Weight & C.G. Calculation 104 3.1.1 ASSUMPTIONS 110 3.1.2 ANALYSIS 111 3.2 VCC Stability Analysis At The Pad 112 3.2.1 MATERIAL MODELS 112 3.2.2 Analysis Methodology 113 3.2.3 Results And Discussion 116 3.3 List Result Summary 136 3.3.1 SSE Condition_SSI Vertical 0.78g 136 3.3.2 SSE Condition_SSI Horizontal 0.88g 136 3.3.3 RLE Condition_SSI VERTICAL 0.89g 137 3.3.4 RLE Condition_SSI Horizontal 1.343g 137 CHAPTER 4. CONCLUSION 138 CHAPTER 5. REFERENCE 139 Appendix A Ansys Ls-Dyna Computer Input and Output Report_0.78g Appendix B Ansys Ls-Dyna Computer Input and Output Report_0.88g Appendix C Ansys Ls-Dyna Computer Input and Output Report_0.89g Appendix D Ansys Ls-Dyna Computer Input and Output Report_1.343g

    (1) Taiwan Power Company. Kuosheng Nuclear Power Station. Independent Spent Fuel Storage Installation (Dry). Project Specification. Revision 1. May 14, 2010.
    (2) NUREG-0800. US NRC Standard Review Plan. 3.7.1 Seismic Design Parameters. Revision 3. March 2007.
    (3) Kuosheng Nuclear Power Station Units 1 and 2 FSAR.
    (4) APA Consulting Computer Code SPECTRUM, Version 2.0.
    (5) APA Consulting Computer Code PSDTH, Version 1.0.
    (6) APA Consulting Computer Code SHAKE91, version 1.0.
    (7) NUREG-0800, US Nuclear Regulatory Commission, Standard Review Plan, Section 3.7.2 Seismic System Analysis, Revision 3.
    (8) NAC Calculation 630075-8001. Development of Acceleration Time Histories. Revision 0.
    (9) Seed H.B., R.T. Wong, I.M. Idriss, and K. Tokimatsu. Moduli and Damping Factors for Dynamic Analyses of Cohesionless Soils. Report No. UCB/EERC-84/14. September 1984.
    (10) Schnabel, P. B., J. Lysmer, and H.B. Seed. SHAKE: A Computer Program for Earthquake Response Analysis of Horizontally Layered Sites. Report No. UCB/EERC-72/12. December 1972.
    (11) APA Consulting Computer Code SPECTRUM, version 2.0.
    (12) APA Consulting Computer Code SASSI, version 1.0.
    (13) APA Consulting Computer Code SPECTRUM, Version 2.0.
    (14) NAC Calculation 630075-8002. Development of Strain Compatible Soil Properties and Surface Time Histories.
    (15) NAC Drawing
    a. NAC Drawing No. 71160-062 R6, ‘Reinforcing Bar and Concrete Placement, Concrete Cask, MAGNASTOR’.
    b. NAC Drawing 0513A-VCC-CIVIL-A004 Rev 2, “BWR MAGNASTOR 27 Cask ISFSI Layout Kuosheng”
    c. NAC Drawing 0513A-VCC-CIVIL-ST103 Rev 0, “Structural Section for Kuosheng ISFSI”
    d. NAC Drawing No. 0513A-VCC-CIVIL-A005 Rev 3, “BWR MAGNASTOR 27 Cask ISFSI Overall Section Kuosheng.
    (16) NAC Calculation 630075-2001, Kuosheng Weight and CG Calculation.
    (17) NAC Calculation 630075-2003.VCC Stability Analysis At The Pad.
    (18) NAC Calculation 630075-8003. Soil-Structure Interaction (SSI) Analysis for the ISFSI Pad.
    (19) 核能二廠用過核子燃料乾式貯存設施因應山腳斷層新事證耐震安全再評估成果報告 泰興工程顧問公司
    (20) 核能二廠用過核子燃料乾式貯存設施因應超越設計基準地震耐震安全再檢核成果報告 泰興工程顧問公司

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