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| 1-2 |
簡介
電廠說明
多樣性/人口
綜合方法
設計及方法觀點
Introduction
Power Plant Description
Varieties/Population
Integrated Approach
Design and Methods Viewpoint
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世界各國以核能發電的發電量比率
Percentage of Total Electricity Provided by the Nuclear Power - by Country (PDF)
各國反應器運作, 建設, 訂製及規劃的狀況
Reactors Operating, Under Construction, Ordered or Planned - by Country (PDF)
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| 3-11 |
反應器壓力容器
說明
應力分析
極限及餘預的設計
脆性斷裂
ASME 碼限制
Reactor Pressure Vessels
Description
Stress Analysis
Design Limits and Margins
Brittle Fracture
ASME Code Limits
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在彈性理論裡的基本關係
Basic Relationships in Elasticity Theory (PDF)
Gill, S.S. 《壓力容器及壓力容器元件的應力分析》 . New York: Pergamon Press, 1970. ISBN: 0080067298.
Gill, S.S. The Stress Analysis of Pressure Vessels and Pressure Vessel Components . New York: Pergamon Press, 1970. ISBN: 0080067298.
Raske, D. T., and C. F. Cheng. 〈304及308號不銹鋼在高溫下的疲勞裂縫擴散〉，《核能技術》 34 (1977).
Raske, D. T., and C. F. Cheng. "Fatigue Crack Propagation in Types 304 and 308 Stainless Steel at Elevated Temperatures." Nuclear Technology 34 (1977).
Ukai, S. Mizuta, S. Kaito, T. Okada, H. 〈20% CW修改的反應器內潛變破裂特性〉，《核能材料月刊》 278, no.2, (2000): 320-327.
Ukai, S. Mizuta, S. Kaito, T. Okada, H. "In-Reactor Creep Rupture Properties of 20% CW Modified." Journal of Nuclear Materials 278, no.2, (2000): 320-327.
Fish, R. L. 〈高光流中子輻射〉，《核能技術》 35 (1977).
Fish, R. L. "High Fluence Nuetron Irradiation." Nuclear Technology 35 (1977).
--- . 〈中子輻射的張力行為〉，《核能技術》 35 (1977).
——— . "Tensile Behavior of Neutron-Irradiation." Nuclear Technology 35 (1977).
Meyer, T. A., K. R. Balkay, andS. E. Yanishko.〈反應器容器的發展PTS - 一個技術發展的催化劑〉，《機械雜誌》 (Jun 1984).
Meyer, T. A., K. R. Balkay, and S. E. Yanishko. "The Evolution of Reactor Vessel PTS - A Catalyst to the Advancement of Technology." Mech. Eng . (Jun 1984).
Brown, S. 〈在反應器壓力容器鋼對抗輻射反應的方法〉 22.314 學期報告 (May 2000).
Brown, S. "Methods to Counteract Radiation Effects on Reactor Pressure Vessel Steels." 22.314 Term Paper Report (May 2000).
〈核能設備規則及標準的設計〉 (僅有精裝本)
"Regulations and Standards for Design of Nuclear Facilities." (Available in hard copy only.)
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| 12 |
近反應結構
融合反應第一屏障 /彈性行為
1. 物理說明
2. 說明的問題
3. 應力及應變
4. 設計用途
Near-Reaction Structures
Fusion Reactor First Walls / Elastic Behavior
1. Physical Description
2. Illustrative Problem
3. Stresses and Deformations
4. Design Use
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| 13-16 |
氧化物燃料棒 / 彈性行為
1. 物理說明
2. 彈性分析
3. 潛變及可塑性
4. 其他特性
Oxide Fuel Rods / Plastic Behavior
1. Physical Description
2. Elastic Analysis
3. Creep and Plasticity
4. Other Features |
Olander, Donald R. 〈附件 - 彈性理論〉，《核能反應器燃料元素的基本觀點》 Springfield, VA: 技術資訊中心, 公共事務辦公室, 能源研究, 及發展管理, 1976.ISBN: 0870790315.
Olander, Donald R. "Appendix - Elasticity Theory." In Fundamental Aspects of Nuclear Reactor Fuel Elements. Springfield, VA: Technical Information Center, Office of Public Affairs, Energy Research, and Development Administration, 1976. ISBN: 0870790315.
---. 〈燃料元素及組件結構性行為的模擬〉，《能反應器燃料元素的基本觀點》 Springfield, VA: 技術資訊中心, 公共事務辦公室, 能源研究, 及發展管理, 1976.ISBN: 0870790315.
———. "Modeling of the Structural Behavior of Fuel Elements and Assemblies." In Fundamental Aspects of Nuclear Reactor Fuel Elements. Springfield, VA: Technical Information Center, Office of Public Affairs, Energy Research, and Development Administration, 1976. ISBN: 0870790315.
〈大量的程式證明 ZIRLO 包覆性能優勢〉，《西屋公司論文》 (僅有紙本拷貝)
"Extensive Programs Demonstrate ZIRLO Cladding performance Benefits." A Westinghouse Brochure. (Available in hard copy only.)
Wallin, H. 〈反應度的燃料棒模型-高燃耗時最初的事故：Transuranus Verses Frey〉，《PSI科學報告》 4 (2001).
Wallin, H. "Fuel Rod Modelling in Reactivity-initiated Accidents at High Burnups: Transuranus Verses Frey." PSI Science Report 4 (2001).
〈Focus XS 與 HTS - 新一代的較高濃縮壓水式燃料組件〉，《西門子核電廠裡的論文》
"Focus XS and HTS - A New Generation of Higher Enrichemnt PWR Fuel Assemblies." A Brochure from Siemens Nuclear Power.
Wallin, H. 〈反應度的燃料棒模型-高燃耗時最初的事故：Transuranus Verses Frey》，《PSI 科學報告》 4 (2001).
Wallin, H. "Fuel Rod Modelling in Reactivity-initiated Accidents at High Burnups: Transuranus Verses Frey." PSI Science Report 4 (2001).
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| 17-19 |
支撐結構與輸送管
核心機械設計
光束方程式
學期討論
疲勞分析
Support Structure & Pipes
Core Mechanical Design
Beam Equations
Discussion of Terms
Fatigue Analysis
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Meyer, J. E. 〈光束理論〉
Meyer, J. E. "Beam Theory." (PDF) |
| 20-22 |
電廠元件的動態分析及地震負載
Dynamic Analysis and Seismic Loads of Plant Components |
Au-Yang, M. K. 《電廠及Process Plant元件流動引起震動：實際操作》 New York: ASME Press, 2001. ISBN: 0791801667.
Au-Yang, M. K. Flow Induced Vibrations of Power and Process Plant Components: A Practical Workbooks. New York: ASME Press, 2001. ISBN: 0791801667.
Herron, R. 〈流動引起震動關係的結論〉 2002. (僅有紙本拷貝.)
Herron, R. "Summary of Important Flow-Induced Vibration Relations." 2002. (Available in hard copy only.)
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| 23-27 |
圍阻體結構
Containment Structures |
Buyukozturk, O. 〈強化水泥結構的非線性分析〉，《電腦與結構》7 (1977).
Buyukozturk, O. "Nonlinear Analysis of Reinforced Concrete Structures." Computers and Structures 7 (1977).
---. 〈水泥結構的影像〉，《NDT & E International》 31 (1998).
———. "Imaging of Concrete Structures." NDT & E International 31 (1998).
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通用單元
Ma, B. M. 〈材料的基本幅射影響〉，摘自《核能反應器材料與應用》. New York, Van Nostrand Reinhold Co., 1983.
Ma, B. M. "Fundamental Radiation Effects on Materials." In Nuclear Reactor Materials and Applications. New York, Van Nostrand Reinhold Co., 1983.
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