• Title/Summary/Keyword: 프레팅 마멸

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Fretting Wear Characteristics of Inconel 690 Tubes in Room Temperature (인코넬 690 튜브의 상온 프레팅 마멸 특성에 대한 연구)

  • Chung, Il-Sup;Lee, Myung-Ho;Chai, Young-Suck
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.33 no.4
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    • pp.329-336
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    • 2009
  • A fretting wear test rig for cross contacting tube specimens, which employs a piezoelectric actuator, has been developed. Along with the simple loading scheme using dead weights, the rig is very simple to be used also. The accuracy was found acceptable. Inconel 690 tubes were tested in room temperature and ambient condition. Normal load and sliding amplitude range up to 35N and $100{\mu}m$, respectively. The sizes of wear scar and the wear volumes were measured, and wear coefficients have been calculated based on those. A study on the fretting wear mechanism of the tubes has been attempted via microscopic observation. Rugged wear surfaces are induced by the separation and adhesion of particles and formation and subsequent fracture of surface layers. Lapped specimens were also tested and abrasive wear seems to be playing a dominant role.

Fretting Wear Characteristics of Nuclear Fuel Rod Material (핵연료봉재의 프레팅 마멸 특성)

  • 김태형;조광희;김석삼
    • Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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    • 1996.04b
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    • pp.25-29
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    • 1996
  • The fretting wear characteristics for Zircaloy-4 tube used as fuel rod in the nuclear power plant have been investigated. The fretting wear tester was designed and manufactured for this experiment. This study was focused on main factors of fretting wear, cycle, slip amplitude and normal load. The worn surfaces were observed by SEM.

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A Study on the Sliding/Impact Wear of a Nuclear Fuel Rod in Room Temperature Air:(I) Development of a Test Rig and Characteristic Analysis (상온 핵연료봉 미끄럼/충격 마멸특성연구:(I) 장치개발 및 특성분석)

  • Lee, Young-Ho;Lee, Kang-Hee;Kim, Hyung-Kyu
    • Proceedings of the KSME Conference
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    • 2007.05a
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    • pp.1859-1863
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    • 2007
  • A new type of a fretting wear tester has been designed and developed in order to simulate the actual vibration behavior of a nuclear fuel rod for springs/dimples in room temperature. When considering the actual contact condition between fuel rod and spring/dimple, if fretting wear progress due to the flow-induced vibration (FIV) under a specific normal load exerted on the fuel rod by the elastic deformation of the spring, the contacting force between the fuel rod and dimple that were located in the opposite side should be decreased. Consequently, the evaluation of developed spacer grids against fretting wear damage should be performed with the results of a cell unit experiments because the contacting force is one of the most important variables that influence to the fretting wear mechanism. Therefore, it is necessary to develop a new type of fretting test rig in order to simulate the actual contact condition. In this paper, the development procedure of a new fretting wear tester and its performance were discussed in detail.

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Improvement of Slip Displacement Evaluation for the Analysis of Tube Fretting Wear (튜브 프레팅마멸 분석을 위한 미끄럼변위 해석방법 개선)

  • Song, Ju-Sun;Kim, Hyung-Kyu;Lee, Young-Ho;Kim, Jae-Hoon
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.67-72
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    • 2004
  • Fundamentally, slip displacement should be known to solve the problem related to the fretting wear. For this, methods for measuring the slip displacement range in the contact surface of the tube and the supports were introduced and analyzed in this study. Also the increment of the slip displacement during a cycle was calculated using the revised formulas. As a result, the slip displacement newly evaluated was much higher ($7{\sim}50$ times) than that previously evaluated especially in the case of the gap existence. This enables to explain the severe wear found when there was a gap between the tube and the supports.

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