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Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions

机译：微动条件下核电蒸汽发生器管支承件的磨损特性

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Sung-hoon Jeong; Young-ze Lee;
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1. Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions [J] . Sung-Hoon Jeong, Young-Ze Lee Diffusion and Defect Data. Solid State Data, Part B. Solid State Phenomena . 2007,第0期

机译：微动条件下核蒸汽发生器管支撑部件的磨损特性
2. Wear Transitions of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions [J] . Sung-Hoon Jeong, Jung-Min Park, Joong-Hui Lee, Key Engineering Materials . 2006,第Pt2期

机译：微动条件下核蒸汽发生器管支撑部件的磨损过渡
3. Wear Transitions of Tube-Support Materials for a Nuclear Steam Generator Through Sliding Wear Test and Fretting Wear Test [J] . Sung-Hoon Jeong, Byoung-Jong Lee, Young-Ze Lee Key Engineering Materials . 2006,第Pt1期

机译：通过滑动磨损试验和微动磨损试验的核蒸汽发生器管支撑材料的磨损过渡
4. Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions [C] . Sung-Hoon Jeong, Young-Ze Lee International Symposium on Safety and Structural Integrity . 2007

机译：在微动条件下核蒸汽发生器管支撑部件的磨损特性
5. The thermalhydraulics of tube-support fouling in nuclear steam generators [D] . Rummens, Helena Elisabeth Cornelia. 1999

机译：核蒸汽发生器中管支撑污垢的热氢气
6. Optical Fiber Demodulation System with High Performance for Assessing Fretting Damage of Steam Generator Tubes [O] . Peijian Huang, Ning Wang, Junying Li, 2018

机译：用于评估蒸汽发生器管微动损伤的高性能光纤解调系统
7. The Thermalhydraulics of tube-support fouling in nuclear steam generators. [O] . Helena Rummens -1

机译：核蒸汽发生器中管支撑污垢的热氢气。
8. Wear behavior of 2-1/4 Cr-1Mo tubing against alloy 718 tube-support material in sodium-cooled steam generators. [R] . W. L. Wilson 1983

机译：在钠冷却蒸汽发生器中，2-1 / 4 Cr-1mo管对合金718管支撑材料的磨损行为。

Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions

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