• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.2047-2052
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• 2004

Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.

• 대한기계학회논문집A
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• 제33권4호
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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.

• Tribology and Lubricants
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• 제22권3호
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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

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2002년도 제35회 춘계학술대회
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• pp.73-79
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• 2002

상온 공기분위기에서 두 가지 형태의 스프링에 대한 연료봉 피복관의 마멸실험을 수행하였으며 다음과 같은 결론을 얻었다. (1) 가장 큰 마멸부피는 스프링 형상이 오목할 경우 틈이 존재할 때 발생하였으며, 형상이 볼록한 경우에는 접촉하중이 존재할 때 마멸부피가 크게 나타났다. (2) 접촉형상이 오목한 형태로 연료봉을 감싸고 있는 경우, 마멸입자의 방출은 다소 어렵게 되며 이에 따라 마열거동은 표면에서 생성되는 마멸입자가 외부로 방출되는 용이성에 따라 최종적으로 마멸부피는 결정된다. (3) 볼록한 형상의 스프링의 경우, 충격마모에 대하여 저항성을 보였으나, 접촉하중이 존재할 경우 높은 마멸량을 보이고 있다. (4) 오목한 형태의 스프링 조건에서 축 방향의 마멸보다는 횡 방향의 마멸량이 더 낮게 나타났다. 이것의 주된 원인은 오목한 형태의 스프링이 충격하중에 있어 가이드역할을 할 가능성이 있는 것으로 나타났다. 또한, 양 방향 모두 마멸입자의 고착 흔적이 나타났으나 횡 방향의 경우 연삭에 의한 경향이 보다 뚜렷이 나타났다.

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2001년도 제33회 춘계학술대회 개최
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• pp.81-88
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• 2001

To study the influence of the shape of contacting bodies (especially the end profile) on slip regime, wear test is conducted in the case of the contact between tube and support. Two different end profiles of the support are used such as truncated wedge and rounded punch. During the test, 10, 30 and 50 N are applied as normal force and slip displacement varies between 10-200 $\mu\textrm{m}$. The tube and the support specimens are made of Zircaloy-4 and a specially designed wear tester is used. Tests are carried out in air at room temperature. Wear on the tube is examined by measuring microscope. Partial and gross slip regimes are classified from the observed wear shape. Surface roughness tester is also used to measure the wear depth and contour, from which wear volume is evaluated. The transition from partial to gross slip is also investigated by investigating the considerable increase of wear volume. From the result, the boundary between the partial and the gross slip is newly determined in the conventional fretting map for the present specific contact configuration. Since the transition is related with the amount of energy dissipation from the contact surface so is wear, it is regarded that wear can be restrained by designing a proper shape of support.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.950-955
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• 2004

Slip displacement is brought into focus to study the tube fretting wear that occurs on the contact by the springs. An oscillating tube was in contact with plate support springs. The contact condition was varied as normal force 5 N, and gaps of 0.1 and 0.2 mm in the experiment. The oscillation range of the tube was also varied as 0.2, 0.3, 0.4 and 0.7 mm. Formulas for predicting the slip displacement range were derived in terms of the vibration amplitudes measured during the tube oscillation. It was found that the slip displacement in transverse direction was much higher ($720{\sim}33000$ times) than that in axial one. This resulted in the severer wear on the contact suffered from transverse slip.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2005년도 창립60주년 기념 추계 학술대회
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• pp.112.2-112.2
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• 2005

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2001년도 제34회 추계학술대회 개최
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• pp.296-303
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• 2001

In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in fretting wear damage due to contacts between the tubes and their supports. In this paper the fretting wear tests and the sliding wear tests were performed using the steam generator tube materials of Inconel 690 against STS 304. Sliding tests with the pin-on-disk type tribometer were done under various applied loads and sliding speeds at air and water environment. Fretting tests were done under various vibrating amplitudes, applied normal loads and various temperatures. From the results of sliding and fretting wear tests, the wear of Inconel 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and often drastically different wear rates can occur. At room temperature, the wear coefficient K of Inconel 690 is 7.57${\times}$10$\^$13/Pa$\^$1/ in air and it is 1.93${\times}$10$\^$13/Pa$\^$1/ in water. At room temperature, it is found that the wear volume in air is more than in water. In water, the wear coefficient K at 50$^{\circ}C$ and 80$^{\circ}C$ is 4.35${\times}$10$\^$-13/Pa$^1$ and 5.81${\times}$10$\^$-13/Pa$^1$ respectively, Therefore, it is found that the wear volume extremely increases by increasing on temperature in water. This study shows that the dissolved oxygen with temperature increment increases and the wear due to fluidity is severe.

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2003년도 학술대회지
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• pp.41-49
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• 2003

Tube oscillation behaviour is experimentally investigated for the study on the fuel rod fretting that is caused by the flow-induced vibration in nuclear reactor. The experiment was conducted in all at room temperature. The specimen of tube assembly was supported by plate springs which simulated the spacer grids and fuel rods of a fuel assembly. To investigate the influence of contact condition between the grids and rods, normal load of 10 and 5 N, gaps of 0.1 and 0.3 mm were applied. The range of the oscillation at the center of the fuel rod specimen was varied as 0.2, 0.3 and 0.4 mm to simulate the fuel rod vibration due to flow. Displacements near the contact were measured with four displacement sensors during the tube oscillation. As results, the shape of oscillation (phase) varied depending on the contact condition. The oscillation displacement increased considerably from the contact to gap condition. The displacement increased further as the gap size increased. It is regarded that the spring shape influences the tube oscillation behaviour. Simple calculation showed that the slip displacement was very small. Therefore, cumulative damage concept is necessary for the fuel rod wear. The mechanism of plowing is thought required to explain the severe wear in the case of gap existence.

• 대한기계학회논문집A
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• 제36권6호
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• pp.637-644
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• 2012

증기 발생기 내부의 U-tube와 지지 구조간의 충격에 의하여 발생하는 프레팅 마모는 원자력 발전소 안전성에 영향을 미치게 된다. 증기발생기의 신뢰성을 향상시키기 위하여 이러한 프레팅 마모 현상을 평가하는 것이 필요하며, 본 연구는 프레팅 마모현상을 정성적, 정량적으로 규명하기 위하여 증기발생기의 실제 상황과 같은 조건의 온도와 압력하에서 실험을 수행하였다. 다양한 실험조건에 대하여 기본적인 실험을 수행하였으며 일률과 마모량의 관계를 온도에 따라 구하였다. $90^{\circ}C$, $200^{\circ}C$, $340^{\circ}C$ 각각의 온도에서의 마모상수는 $9.051{\times}10^{-16}\;Pa^{-1}$, $3.009{\times}10^{-15}\;Pa^{-1}$, $2.235{\times}10^{-15}\;Pa^{-1}$로 구해졌으며 특히 저온 수중상태의 마모상수는 물의 점도의 영향으로 상온 공기중의 값보다 작은 것으로 나타났다.