• Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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• 1999.11a
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• pp.78-83
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• 1999

Fretting Wear Behavior and Characteristics were investigated with Inconel 690 tube which is used in Nuclear Power Plant. Fretting Wear Tester has been engaged in the study of characteristics on tube fretted induced to various factors, i.e. vibration amplitude, contact type, material properties load support geometry, environmental effect Test has been performed in air and at room temperature. Wear volume rate has been approximately estimated as a function of normal load.

• Proceedings of the KSME Conference
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• 2005.11a
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• pp.110.2-110.2
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• 2005

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2010.05a
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• pp.1467-1468
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• 2010

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2009.10a
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• pp.447-448
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• 2009

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.489-495
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• 1998

최근 울진 1,2호기의 급정지 제어봉 E.C.T(Eddy Current Test) 결과 Fretting Wear가 심한 것이 관찰되었다. 이는 유동유발 진동에 의해 제어봉과 그 지지물 간의 접촉으로 인한 손상이 주요인으로 추정되고 있다. 제어봉 손상은 제어봉 교체로 인한 비용뿐만 아니라 마모금속의 방사화로 인한 냉각재의 오염을 수반한다. 따라서 본 연구는 원자로의 유동유발진동을 선별하여 파손 위치 및 형태, 유동조건, 제어봉과 안내관의 기하학적 구조 등을 분석한 결과 지배적인 손상원인을 Turbulence Excitation과 Fluidelastic Instability로 선정하였다. 특히 안내관내의 6번째 card 위치에서 발생하는 높은 마모현상이 난류도 증가에 의한 손상임을 제시하였다

• Tribology and Lubricants
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• v.22 no.3
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• pp.144-148
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• 2006

The experimental investigation was performed to find the associated changes in characteristics of fretting wear with various water temperatures. The fretting wear tests were carried out using the zirconium alloy tubes and the grids with increasing the water temperature. The tube materials in water of $20^{\circ}C,\;50^{\circ}C\;and\;80^{\circ}C$ were tested with the applied load of 20 N and the relative amplitude of $200{\mu}m$. The worn surfaces were observed by SEM, EDX analysis and 2D surface profiler. As the water temperature increased, the wear volume was decreased, but oxide layer was increased on the worn surface. The abrasive wear mechanism was observed at water temperature of $20^{\circ}C$ and adhesive wear mechanism occurred at water temperature of $50^{\circ}C,\;80^{\circ}C$. As the water temperature increased, surface micro-hardness was decreased, but wear depth and wear width were decreased due to increasing stick phenomenon. Stick regime occurred due to the formation of oxide layer on the worn surface with increasing water temperatures

• Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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• 2002.05a
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• pp.73-79
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• 2002

Fretting wear test in room temperature air was performed to evaluate the wear mechanism of fuel rod using a fretting wear tester, which has been developed for experimental study. The main focus was to compare the wear behaviors of fuel rod against support springs at different contact geometries (i.e. concave and convex) and slip directions (axial and transverse). The wear on the tube was examined by the surface roughness tester, which measures the volume. The result indicated that with change of contact geometry from 5N of normal load to 0.1mm gap, wear volume of tube Increased in the condition of concave spring, but slowly decreased in convex spring. From the results of SEM observation, wear mechanism of each test condition was also depend on the above contact parameters. The wear mechanism of each test condition in room temperature air is discussed.

• Nuclear Engineering and Technology
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• v.52 no.6
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• pp.1304-1317
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• 2020

The tubes in a heat exchanger, such as a steam generator (SG), are subjected to crossflow, and interaction between tubes and supports can happen, which can cause fretting wear of tubes. Although many experiments and models have been established, some detailed mechanisms are still not sufficiently clear. In this work, more attention is paid to obtain the regulation of impact and sliding in the complex process and many factors, such as excitation forces and clearances. The responses and contact forces were analyzed to obtain clear understanding of the influences of these factors. Room temperature tests in the air were established. The results show that the effect of clearance on the normal work rate is not monotonous and instead has two peaks. The force ratio can influence the normal work rate by changing the distribution of contact angles, which can result in higher sliding in the contact process. Fretting wear tests are conducted, and the wear surfaces are analyzed by a scanning electron microscope (SEM) and energy dispersive X-ray spectrometer (EDX). The results of this work can serve as a reference for impactsliding contact analysis between AVBs and tubes in steam generators.

• Nuclear Engineering and Technology
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• v.28 no.1
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• pp.17-26
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• 1996

The in-reactor fuel rod support conditions against the fretting wear-induced damage can be evaluated by residual spacer grid spring deflection or rod-to-grid gap. In order to evaluate the impact of fuel design parameters on the fretting wear-induced damage, a simulation methodology of the in-reactor fuel rod supporting conditions as a function of burnup has been developed and implemented in the GRIDFORCE program. The simulation methodology takes into account cladding creep rate, initial spring deflection, initial spring force, and spring force relaxation rate as the key fuel design parameters affecting the in-reactor fuel rod supporting conditions. Based on the parametric studies on these key parameters, it is found that the initial spring deflection, the spring force relaxation rate and cladding creepdown rate are in the order of the impact on the in-reactor fuel rod supporting conditions. Application of this simulation methodology to the fretting wear-induced failure experienced in a commercial plant indicates that this methodology can be utilized as an effective tool in evaluating the capability of newly developed cladding materials and/or new spacer grid designs against the fretting wear-induced damage.

• Journal of the Korean Institute of Gas
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• v.3 no.3 s.8
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• pp.39-44
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• 1999

In the study, corrosion characteristics under various corrosion environments(neutral solution, acid solution), for various hinge materials(SM20C, BsC3 and STC4H), were investigated by immersion test, and the behaviour of fretting wear under atmosphere was studied. In immersion test, corrosion potential of those materials showed to be noble in the sequence of $0.5\%HNO_3$> underground water> $0.5\%\;H_2SO_4$ solution, and potential of a sole material, except BsC3, was more noble than these of mixed materials. In same material SM20C, the fretting wear loss of rotary materials increased about 1.9 times to that of moving materials, because of surface hardening by frictional force.