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| 1-2 |
简介
电厂说明
多样性/人口
综合方法
设计及方法观点
Introduction
Power Plant Description
Varieties/Population
Integrated Approach
Design and Methods Viewpoint
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世界各国以核能发电的发电量比率
Percentage of Total Electricity Provided by the Nuclear Power - by Country (PDF)
各国反应器运作, 建设, 订制及规划的状况
Reactors Operating, Under Construction, Ordered or Planned - by Country (PDF)
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| 3-11 |
反应器压力容器
说明
应力分析
极限及余预的设计
脆性断裂
ASME 码限制
Reactor Pressure Vessels
Description
Stress Analysis
Design Limits and Margins
Brittle Fracture
ASME Code Limits
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在弹性理论里的基本关系
Basic Relationships in Elasticity Theory (PDF)
Gill, S.S. 《压力容器及压力容器元件的应力分析》 . 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号不锈钢在高温下的疲劳裂缝扩散〉，《核能技术》 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修改的反应器内潜变破裂特性〉，《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. 〈高光流中子辐射〉，《核能技术》 35 (1977).
Fish, R. L. "High Fluence Nuetron Irradiation." Nuclear Technology 35 (1977).
--- . 〈中子辐射的张力行为〉，《核能技术》 35 (1977).
——— . "Tensile Behavior of Neutron-Irradiation." Nuclear Technology 35 (1977).
Meyer, T. A., K. R. Balkay, andS. E. Yanishko.〈反应器容器的发展PTS - 一个技术发展的催化剂〉，《机械杂志》 (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. 〈在反应器压力容器钢对抗辐射反应的方法〉 22.314 学期报告 (May 2000).
Brown, S. "Methods to Counteract Radiation Effects on Reactor Pressure Vessel Steels." 22.314 Term Paper Report (May 2000).
〈核能设备规则及标准的设计〉 (仅有精装本)
"Regulations and Standards for Design of Nuclear Facilities." (Available in hard copy only.)
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| 12 |
近反应结构
融合反应第一屏障 /弹性行为
1. 物理说明
2. 说明的问题
3. 应力及应变
4. 设计用途
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 / 弹性行为
1. 物理说明
2. 弹性分析
3. 潜变及可塑性
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 - 弹性理论〉，《核能反应器燃料元素的基本观点》 Springfield, VA: 技术资讯中心, 公共事务办公室, 能源研究, 及发展管理, 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.
---. 〈燃料元素及组件结构性行为的模拟〉，《能反应器燃料元素的基本观点》 Springfield, VA: 技术资讯中心, 公共事务办公室, 能源研究, 及发展管理, 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.
〈大量的程式证明 ZIRLO 包覆性能优势〉，《西屋公司论文》 (仅有纸本拷贝)
"Extensive Programs Demonstrate ZIRLO Cladding performance Benefits." A Westinghouse Brochure. (Available in hard copy only.)
Wallin, H. 〈反应度的燃料棒模型-高燃耗时最初的事故：Transuranus Verses Frey〉，《PSI科学报告》 4 (2001).
Wallin, H. "Fuel Rod Modelling in Reactivity-initiated Accidents at High Burnups: Transuranus Verses Frey." PSI Science Report 4 (2001).
〈Focus XS 与 HTS - 新一代的较高浓缩压水式燃料组件〉，《西门子核电厂里的论文》
"Focus XS and HTS - A New Generation of Higher Enrichemnt PWR Fuel Assemblies." A Brochure from Siemens Nuclear Power.
Wallin, H. 〈反应度的燃料棒模型-高燃耗时最初的事故：Transuranus Verses Frey》，《PSI 科学报告》 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 |
支撑结构与输送管
核心机械设计
光束方程式
学期讨论
疲劳分析
Support Structure & Pipes
Core Mechanical Design
Beam Equations
Discussion of Terms
Fatigue Analysis
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Meyer, J. E. 〈光束理论〉
Meyer, J. E. "Beam Theory." (PDF) |
| 20-22 |
电厂元件的动态分析及地震负载
Dynamic Analysis and Seismic Loads of Plant Components |
Au-Yang, M. K. 《电厂及Process Plant元件流动引起震动：实际操作》 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. 〈流动引起震动关系的结论〉 2002. (仅有纸本拷贝.)
Herron, R. "Summary of Important Flow-Induced Vibration Relations." 2002. (Available in hard copy only.)
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| 23-27 |
围阻体结构
Containment Structures |
Buyukozturk, O. 〈强化水泥结构的非线性分析〉，《计算机与结构》7 (1977).
Buyukozturk, O. "Nonlinear Analysis of Reinforced Concrete Structures." Computers and Structures 7 (1977).
---. 〈水泥结构的影像〉，《NDT & E International》 31 (1998).
———. "Imaging of Concrete Structures." NDT & E International 31 (1998).
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通用单元
Ma, B. M. 〈材料的基本幅射影响〉，摘自《核能反应器材料与应用》. 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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