• 한국산업안전학회:학술대회논문집
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• 한국안전학회 2002년도 춘계 학술논문발표회 논문집
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• pp.184-189
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• 2002

기계부품 및 구조물의 상호접촉면이 미소변위에 의해 상대운동을 할 때 접촉면에서는 마모가 발생하고 이러한 마모현상은 당해 구조물의 안전성을 심각하게 위협하는 결과를 초래하게 된다. 이러한 마모 현상에 대한 근래의 연구동향으로는 $Engel^{(1.2)}$ 이 충격(impact)에 의한 마모에 대해, 그리고 $Waterhouse^{(3)}$ 는 미끄럼(sliding) 마모에 대해 연구한 바 있다. 원자력발전소의 증기발생기(steam generator) 내에서 1차측의 세관(tube)과 2차측에 속하는 지지물(supporter) 또는 방진대(antivibration band) 사이에서 세관의 진동으로 인해 지지물과 충돌을 일으키고 충돌 횟수가 누적되면 세관의 마모로 이어져 결국 세관의 건전성은 침해받게 된다.(중략)

• Restorative Dentistry and Endodontics
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• 제27권6호
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• pp.555-560
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• 2002

치근부 민감성 (hypersensitivity)은 부분적으로 치근면에서의 개방된 상아세관이 존재하는 것에 기인한다고 생각되며 이러한 치근부의 개방된 상아세관은 치경부 병소 (cervical lesion)에 주로 존재하는데 이는 칫솔질에 의한 마모(toothbrush abrasion), 화학적 침식 (chemical erosion), 또는 abfraction 등의 결과로 나타난다고 한다. 이미 Nd-YAG 레이저를 이용한 실험에서 레이저를 조사한 상아질 표면의 상아 세관 구경이 감소되고 상아세관의 폐쇄가 많이 증가되는 양상을 관찰한 바 있다. 이 실험의 목적은 고출력레이저인 Nd-YAC 레이저를 이용한 상아질 표면처치의 임상사용가능성을 좀 더 상세히 평가하기 위해 상아질에 레이저를 처리한 후 기계적으로 마모시킨 경우 상아질 표면의 변화를 관찰하는 것이다. 50개의 발치된 치아의 상아질을 노출시켜 표면을 연마한 후 대조군에서는 37% 인산으로 산부식하여 상아 세관을 노출시킨 후 레이저를 조사하였고, 실험군에서는 대조군과 같은 조건으로 산과 레이저로 처리된 상아질 표면을 15, 45, 90 그리고 180분 동안 전동 칫솔로 기계적으로 마모시켜 그 표면을 주사전자현미경으로 관찰한 결과, 대조군, 칫솔질을 15, 45분간 시행한 실험군에서는 상아 세관 입구가 10% 이내에서 노출되었고 50 그리고 180분간 칫솔질을 시행한 실험군에서는 45 그리고 48%의 상아세관 입구의 노출이 관찰되었다. 그러므로 Nd-YAC레이저의 조사는 상아질 표면에서 축적 시간이 45분 이상에서 90분 이하인 기계적 마모에 의한 상아 세관 입구의 노출을 억제할 수 있을 것이라 사료된다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.84-89
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• 2004

When the tube contacted to support, anti-vibration bar of the steam generator in nuclear power plant, the contact area is worn out by their relative displacement and contact force. Connors and Au-Yang found the relation between tube worn displacement and volume, or normal work rate at given gap size. The present analysis is obtained the relation between tube worn displacement and normal work rate at various gap size modifying Au-Yang's result. The results are compared with Connors and Yettisir and Pettigrew's results. The comparison shows that Yettisir and Pettigrew result is fairly good agreement with Connors and present results with gap clearance, 0.015in.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 추계학술대회
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• pp.1168-1173
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• 2003

When the tube contacted to support and antivibration bar of the steam generator in unclear power plant, the contact area is worn out by their relative displacement. In the study, wear depths of the tube inclined to tube support and antivibration bar are approximately predicted by a method using the contact load and relative displacement. In the case of the inclined contact, the results show wear depths of the steam generator tube predicted by the impact model are larger than those by the sliding model.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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• pp.302-307
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• 2004

The major flow-induced vibration mechanisms such as fluid-elastic and turbulence excitation can cause the various types of wear of the steam generator tubes in unclear power plant. It is generally accepted that the tube wear due to vibration is affected by the presence of gap clearance between tube and support plate. Connors showed that the tube wear depth could be estimated by using the relationship between wear volume and sliding distance for contact time. Au-Yang predicted the wear depth by using the nonlinear characteristics of normal work rate to contact time. In this study the effect of gap size on the steam generator tubes wear is analyzed by deriving the wear depth versus normal work rate relationship from these previous results.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.343.2-343
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• 2001

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회A
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• pp.1684-1689
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• 2007

Fretting wear is one of the important degradation mechanisms of steam generator tubes in the nuclear power plants. Especially, impact fretting wear occurred between steam generator tubes and tube support plates or anti-vibration bar. Various tests have been carried out to investigate the wear mechanisms and to report the wear coefficients. Those are fruitful to get insight for the wear damage of steam generator tubes; however, most wear researches have concentrated on sliding wear of the steam generator tubes, which may not represent the wear loading modes in real plants. In the present work, impact fretting tests of steam generator tube were carried out. A wear progression model for impact-fretting wear has been investigated and proposed. The proposed wear progression model of impact-fretting wear is as follows; oxide film breaking step at the initial stage, and layer formation step, energy accumulation step and finally particle torn out step which is followed by layer formation in the stable impact-fretting progress. The wear coefficient according to the work-rate model has been also compared with one between tube and support.

• 대한기계학회논문집A
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• 제32권10호
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• pp.817-822
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• 2008

Fretting wear is one of the important degradation mechanisms of steam generator tubes in the nuclear power plants. Especially, impact fretting wear occurred between steam generator tubes and tube support plates or anti-vibration bar. Various tests have been carried out to investigate the wear mechanisms and to report the wear coefficients. Those are fruitful to get insight for the wear damage of steam generator tubes; however, most wear researches have concentrated on sliding wear of the steam generator tubes, which may not represent the wear loading modes in real plants. In the present work, impact fretting tests of steam generator tube were carried out. A wear progress model for impact-fretting wear has been investigated and proposed. The proposed wear progress model of impact-fretting wear is as follows; oxide film breaking step at the initial stage, and layer formation step, energy accumulation step and finally particle torn out step which is followed by layer formation in the stable impact-fretting progress. The wear coefficient according to the work-rate model has been also compared with one between tube and support.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.395.1-395
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• 2002

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.178-188
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• 2003

The wear of steam generator tubes is due to the vibration occurred between tubes and tube supporters. To predict the future wear depth, the wear constants of the impact and the sliding model is used. The wear constants, 3C/2 and K/3H, are found inversely from known wear depth and time. Using these constants, the future wear depths are found from two bodies that deform the elliptical shape. The results are compared with the measured wear depth of steam generator tubes in a nuclear power plant. The results show that the predicted wear depth envelopes the measured wear depth.