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부식된 핵연료 피복관과 지지격자 사이의 프레팅 마멸 특성
김진선,박세민,김용환,이승재,이영제,Kim, Jin-Seon,Park, Se-Min,Kim, Yong-Hwan,Lee, Seung-Jae,Lee, Young-Ze 한국트라이볼로지학회 2007 한국윤활학회지(윤활학회지) Vol.23 No.3
Fuel cladding tubes in nuclear fuel assembly are held up by supporting grids because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube and support. The fretting wear of tube and support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. The fretting wear tests were performed with supporting grids and cladding tubes, especially after corrosion treatment on tubes, in water. The tests were done using various applied loads with fixed amplitude. From the results of fretting tests, the wear amounts of tube materials can be predictable by obtaining the wear coefficient using the work rate model. Due to stick phenomena the wear depth was changed as increasing load and temperature. The maximum wear depth was decreased as increasing the water temperatures. At high temperatures there are the regions of some severe adhesion due to stick phenomena.
피복관 재료와 지지격자 형상에 따른 핵연료봉 피복관의 마멸거동에 관한 연구
김대정(Dae-Jung Kim),용석주(Suk-Ju Yong),정성훈(Sung-Hoon Jeong),이영제(Young-Ze Lee),김일규(Il-Kyu Kim) 한국트라이볼로지학회 2003 한국트라이볼로지학회 학술대회 Vol.36 No.-
Fretting is the small-amplitude oscillatory motion, usually tangential, between two solid surfaces in contact. fretting wear is wear arising as a result of fretting. In nuclear power plant, high flow rates can induce vibration of the nuclear fuel rod cladding tubes resulting in fretting wear damage due to contacts between the tubes and their supports. In this paper the sliding wear' tests and fretting wear tests were performed in water at room temperature. Sliding tests with the pin-on-disk type tribometer were done using nuclear fuel rod cladding tube materials of Zirconium and Zircaloy-4 alloy series against STS 304 under various applied loads. Fretting tests were done using some different tube materials and supporting grid shapes under various applied loads. From the results of sliding and fretting wear tests, the wear of tube materials can be predictable by obtaining wear coefficient using the work rate model. Depending on various normal load, tube materials, and supporting grid shapes, distinctively different wear scars of fretting and stick-slip mechanism can occur.
Chi-Yong Park(박치용),Jeong-Keun Lee(이정근) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
Fretting wear is one of the important degradation mechanisms of steam generator(SG) tubes in the nuclear power plants. Understanding of tube wear characteristics is important to keep the integrity of the SG tubes to secure the safety of the nuclear power plants. Experimental examination has been performed for the purpose of investigating the impact fretting phenomena by using an advanced wear facility, which is able to simulate tube motion and circumstances of operating tubes. Test material is Alloy 690 tube and 409 stainless steel tube supports. From the results of experiments, wear scar progression is investigated in the case of impact-fretting wear test of SG tubes at plant operating conditions such as pressure of 15㎫, high temperature of 290 ℃ and low dissolved oxygen. Hammer imprint that is actual damaged wear pattern, has been observed on the worn surface. From investigation of wear scar pattern, wear mechanism was initially the delamination wear due to cracking the hard oxide film and finally transferred to the stable impact-fretting patterns.
이상 유동환경에서의 증기 발생기 세관의 프레팅 마모 특성평가
박정민(JungMin Park),정성훈(Sung Hoon Jeong),이영제(Young Ze Leek) 한국트라이볼로지학회 2007 한국트라이볼로지학회 학술대회 Vol.2007 No.6
Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. This work is focused on the influence of two phase flow on the wear amount of tube-support material at room temperature. The tube and support materials were Inconel 690 and 409 SS, respectively. The wear tests were conducted in various environments, which are in water without flow, in flowing water and in flowing water with air. The results showed that the flow of water influenced on the decrease of the wear-life of tube comparing with in water without flow.
부식된 핵연료 피복관과 지지격자 사이의 프레팅 마멸 특성
김진선(Jin-Seon Kim),박세민(Se-Min Park),김용환(Yong-Hwan Kim),이승재(Seung-Jae Lee),이영제(Young-Ze Lee) 한국트라이볼로지학회 2008 한국트라이볼로지학회지 (Tribol. Lubr.) Vol.24 No.3
Fuel cladding tubes in nuclear fuel assembly are held up by supporting grids because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FlV (flow induced vibration), which causes fretting wear in contact parts of tube and support. The fretting wear of tube and support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. The fretting wear tests were performed with supporting grids and cladding tubes, especially after corrosion treatment on tubes, in water. The tests were done using various applied loads with fixed amplitude. From the results of fretting tests, the wear amounts of tube materials can be predictable by obtaining the wear coefficient using the work rate model. Due to stick phenomena the wear depth was changed as increasing load and temperature. The maximum wear depth was decreased as increasing the water temperatures. At high temperatures there are the regions of some severe adhesion due to stick phenomena.
Park, Dong-Shin,Park, Jung-Min,Kim, Jin-Seon,Lee, Young-Ze Korean Tribology Society 2009 KSTLE International Journal Vol.10 No.1
The nuclear steam generator is composed of a bundle of tubes. The length of these tubes is very long, but their diameter is small. Fluid exists inside of the steam generator and its flow causes vibration, therefore these tubes are supported by anti-vibration bars. The wear damage due to the vibration is known as fretting wear, which should be minimized to ensure the safety of the plants. Research needs to be done about decreasing the amount of fretting wear. Hard coatings have proven to be very effective in reducing the amount of wear. The commercial coatings of TiN and CrN have excellent wear resistance and are used to protect the Inconel tube from fretting wear. The tube-on-flat type tester was used for conducting the fretting wear tests. It was found that the wear amounts of the coated tubes decreased depending on the coating thickness. CrN was found to be very effective in reducing the wear, while the wear amounts were dependent on the coating thickness in the case of TiN and a thick coating of TiN was very effective on wear resistance.
Dong-Shin Park,Jung-Min Park,Jin-Seon Kim,Young-Ze Lee 한국트라이볼로지학회 2009 KSTLE International Journal Vol.10 No.1/2
The nuclear steam generator is composed of a bundle of tubes. The length of these tubes is very long, but their diameter is small. Fluid exists inside of the steam generator and its flow causes vibration, therefore these tubes are supported by anti-vibration bars. The wear damage due to the vibration is known as fretting wear, which should be minimized to ensure the safety of the plants. Research needs to be done about decreasing the amount of fretting wear. Hard coatings have proven to be very effective in reducing the amount of wear. The commercial coatings of TiN and CrN have excellent wear resistance and are used to protect the Inconel tube from fretting wear. The tube-on-flat type tester was used for conducting the fretting wear tests. It was found that the wear amounts of the coated tubes decreased depending on the coating thickness. CrN was found to be very effective in reducing the wear, while the wear amounts were dependent on the coating thickness in the case of TiN and a thick coating of TiN was very effective on wear resistance.
CrN과 TiN 코팅을 적용한 증기 발생기 세관의 프레팅 마모에 대한 연구
박정민(Jung-Min Park),정성훈(Sung-Hoon Jeong),김진선(Jin-Seon Kim),박세민(Se-Min Park),이영제(Young-Ze Lee) 한국트라이볼로지학회 2008 한국윤활학회지(윤활학회지) Vol.24 No.5
The steam generator of nuclear power plant is composed with the bundles of long tubes. It is exposed fluid flow and weak in the vibration. The tubes are supported by anti-vibration bars. Due to vibration the wear damage is called as the fretting wear. It should be minimized for the safety of the plants. The hard coatings are very effective to reduce the amount of wear. The coatings of TiN and CrN are introduced in this study to protect the fretting surfaces. The tube-on-flat type tester was used for fretting wear tests. The results show that the wear amounts of the coated tubes were decreased depending on coating thickness. CrN was very effective to reduce the wear. In case of TiN the wear amounts were dependent on the coating thickness. Thick coating of TiN was very effective for wear resistance.
이상 유동 환경이 증기 발생기 세관과 지지대의 프레팅 마모에 미치는 영향에 대한 연구
박정민(Jung-Min Park),정성훈(Sung-Hoon Jeong),김진선(Jin-Seon Kim),박세민(Se-Min Park),이영제(Young-Ze Lee) 한국트라이볼로지학회 2008 한국윤활학회지(윤활학회지) Vol.24 No.6
Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. The tube and support materials were Inconel 690 and STS 409. The wear tests were conducted in various environments, which are in water without flow, in flowing water and in flowing water with air. The results showed that the flow of water influenced on the wear-life of tube. The wear-life of tube decreased in water flow as compared with wear-life in stationary water.
Prediction of Fretting Wear Depth for Steam Generator Tubes Based on Various Types of Wear Scars
RYU, Ki-Wahn,PARK, Chi-Yong,KIM, Hyung-Nam,RHEE, Huinam Atomic Energy Society of Japan 2010 Journal of nuclear science and technology Vol.47 No.5
<P>Calculations of fretting wear depth due to the turbulence excitation around steam generator tubes, for various wear scars, are carried out numerically. Four typical wear topologies, namely, round-, crescent-, flat-, and oblique-shaped wear scars, are adopted to represent the configuration of the wear volume. Oblique wear shows the most severe case for the wear time history, whereas both round- and crescent-shaped wears have smaller increasing rates of wear histories than flat- or oblique-shaped wears. It can be estimated that a high cross flow, around the U-bend region of the steam generator tube, significantly enhances the wear phenomena because the basic wear scar, at the contact point between the tube and its support, is flat or oblique. Parametric studies on the inclined angle and radial clearance are also carried out for oblique and crescent wear shapes.</P>