• 제목/요약/키워드: mechanical break

검색결과 460건 처리시간 0.024초

잔류응력의 표면파손과 마멸에 대한 영향 (The Effect of Residual Stresses on Surface Failure and Wear)

  • 이영제;김진욱
    • 대한기계학회논문집A
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    • 제26권4호
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    • pp.677-682
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    • 2002
  • Break-in is an intentional treatment to enhance the performance life of machinery parts and to maintain static friction behavior. Most studies on break-in have concerned only about surface conditions such as roughness or film formation. But the exact mechanism of break-in has not been found yet. Friction, scuffing behavior and wear of AISI 1045 were studied in relation to break-in and residual stress. The cylinder-on-disk type tribometer was used with the line-contact geometry. Scuffing tests were carried out using a constant load of 730N. In the break-in procedure the step load was applied from 100N to 200N. In this experiment, it was found that the break-in helps compressive residual stress to be formed well enough to enhance the scuffing life during the scuffing test. Specimens that had high compressive residual stress induced by shot-peening show better wear resistance than those were not shot-peened. Results of scuffing test, break-in procedure and wear amount in relation to residual stress have been discussed.

실리콘 웨이퍼 연마에서의 Break-in 모니터링 (Monitoring of Break-in time in Si wafer polishing)

  • 정석훈;박범영;박성민;이상직;이현섭;정해도;배소익;최은석;백경록
    • 한국전기전자재료학회:학술대회논문집
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    • 한국전기전자재료학회 2005년도 추계학술대회 논문집 Vol.18
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    • pp.360-361
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    • 2005
  • Rapid progress in IC fabrication technology has strong demand in polishing of silicon wafer to meet the tight specification of nanotopography and surface roughness. One of the important issues in Si CMP is the stabilization of polishing pad. If a polishing pad is not stabilized before main Si wafer polishing process, good polishing result can not be expected. Therefore, new pad must be subjected into break-in process using dummy wafers for a certain period of time to enhance its performance. After the break-in process, the main Si wafer polishing process must be performed. In this study, the characteristics of break-in process were investigated in Si wafer polishing. Viscoelastic behavior, temperature variation of pad and friction were measured to evaluate the break-in phenomenon. Also, it is found that the characteristic of the break-in seems to be related to viscoelastic behavior of pad.

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Matlab과 PSPICE를 이용한 동기전동기의 전기 제동 확대 시뮬레이션에 관한 연구 (A study on electronic braking expansion simulation of synchronous motor applied by Matlab & PSPICE)

  • 나승권;구기준
    • 한국컴퓨터정보학회논문지
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    • 제17권2호
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    • pp.87-94
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    • 2012
  • 기계적 제동방식이 사용되는 전동차는 공기제동과 전기제동을 혼합한 방식으로 최근 녹색성장을 지향하면서 효율개선 및 환경문제 해결을 위한 많은 방법들이 제시되고 있다. 기계적인 제동은 분진, 소음 등의 환경문제와 함께 브레이크 슈와 라이닝 등의 소모품을 교체해야하는 경제적 문제를 가지고 있다. 이러한 단점을 보완하기 위하여 고속 영역에서 정지에 이르는 광범위한 영역에 이르기까지의 전기제동을 필요로 하게 되었다. 본 연구는 구배에 의한 부하토오크를 추정하여 전동차를정지시키는방법에대해연구되어졌으며낙차에따른 토오크를 추정하여 제동하는 방법의 특성을 확인하였다.

회귀분석에 의한 모터싸이클 브레이크 디스크의 열변형량에 관한 연구 (A Study on Thermal Deformation Volume of Motorcycle Brake Disk using Regression Analysis)

  • 류미라;변상민;박흥식
    • Tribology and Lubricants
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    • 제25권2호
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    • pp.102-107
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    • 2009
  • The thermal deformation volume of motorcycle break disk was studied using a disk-on-pad type friction tester. Thermal deformation volume of motorcycle break disk have an effect on the frictional factor such as applied load, sliding speed, sliding distance and number of ventilated disk hole. However, it is difficult to know the mutual relation of these factors on thermal deformation volume. In this study, the thermal deformation volume with ANSYS workbench are obtained by application of temperature from mechanical test. From this study, the result was shown that the motorcycle break disk with ventilated hole 3 have the most excellent thermal deformation characteristics. The regression equation with frictional factors which have a trust rate of 95% for prediction of thermal deformation volume of motorcycle break disk was composed.

표면크랙의 관통 및 파단 피로수명 예측 (Prediction of Penetration and Break Fatigue Life of Surface Crack)

  • 윤한용
    • 대한기계학회논문집
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    • 제16권8호
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    • pp.1446-1450
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    • 1992
  • 본 연구에서는 윤, H. Okamura는 주어진 초기크랙으로부터 관통이전의 한계크 랙까지의 수명을 간단히 평가하는 수법을 제안했으며 또한, 파괴역학적 제인자의 수명 에 미치는 영향을 평가했다. 본 논문은 이러한 연구들의 연장으로서 상기 남등의 응 력 확대 계수 평가식을 이용하여 파단수명의 예측수법을 확립하고 파단수명에 미치는 파괴역학적 제인자의 영향을 밝히는데 그 목적을 두고 있다.

Axial response of PWR fuel assemblies for earthquake and pipe break excitations

  • Jhung, Myung J.
    • Structural Engineering and Mechanics
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    • 제5권2호
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    • pp.149-165
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    • 1997
  • A dynamic time-history analysis of the coupled internals and core in the vertical direction is performed as a part of the fuel assembly qualification program. To reflect the interaction between the fuel rods and grid cage, friction element is developed and is implemented. Also derived here is a method to calculate a hydraulic force on the reactor internals due to pipe break. Peak responses are obtained for the excitations induced from earthquake and pipe break. The dynamic responses such as fuel assembly axial forces and lift-off characteristics are investigated.

Application of the Leak Before Break(LBB) Concept to a Heat Exchanger in a Nuclear Power Plant

  • Kwon, Jae-Do;Lee, Choon-Yeol;Lee, Yong-Son;Sul, Il-Chan
    • Journal of Mechanical Science and Technology
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    • 제15권1호
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    • pp.10-20
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    • 2001
  • The leak before break(LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount(approximately 37.9 liters) containing the radioactive material which can activate the radiation detector device installed in near the heat exchanger is assumed. A postulated initial flaw size that can not grow to a critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural integrity of the heat exchanger is not impeded. Particularly the informational scenario presented in this paper discusses an actual nuclear plant.

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Numerical prediction of transient hydraulic loads acting on PWR steam generator tubes and supports during blowdown following a feedwater line break

  • Jo, Jong Chull;Jeong, Jae Jun;Yun, Byong Jo;Kim, Jongkap
    • Nuclear Engineering and Technology
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    • 제53권1호
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    • pp.322-336
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    • 2021
  • This paper presents a numerical prediction of the transient hydraulic loads acting on the tubes and external supports of a pressurized water reactor (PWR) steam generator (SG) during blowdown following a sudden feedwater line break (FWLB). A simplified SG model was used to easily demonstrate the prediction. The blowdown discharge flow was treated as a flashing flow to realistically simulate the transient flow fields inside the SG and the connected broken feedwater pipe. The effects of the SG initial pressure or the broken feedwater pipe length on the intensities or magnitudes of transient hydraulic loads were investigated. Then predictions of the decompression pressure wave-induced impulsive pressure differential loads on SG tubes and the transient blowdown loads on SG external supports were demonstrated and the general aspects of transient responses of such transient hydraulic loads to the FWLB were discussed.

Dynamic load concentration caused by a break in a Lamina with viscoelastic matrix

  • Reza, Arash;Sedighi, Hamid M.;Soleimani, Mahdi
    • Steel and Composite Structures
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    • 제18권6호
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    • pp.1465-1478
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    • 2015
  • The effect of cutting off fibers on transient load in a polymeric matrix composite lamina was studied in this paper. The behavior of fibers was considered to be linear elastic and the matrix behavior was considered to be linear viscoelastic. To model the viscoelastic behavior of matrix, a three parameter solid model was employed. To conduct this research, finite difference method was used. The governing equations were obtained using Shear-lag theory and were solved using boundary and initial conditions before and after the development of break. Using finite difference method, the governing integro-differential equations were developed and normal stress in the fibers is obtained. Particular attention is paid the dynamic overshoot resulting when the fibers are suddenly broken. Results show that considering viscoelastic properties of matrix causes a decrease in dynamic load concentration factor and an increase in static load concentration factor. Also with increases the number of broken fibers, trend of increasing load concentration factor decreases gradually. Furthermore, the overshoot of load in fibers adjacent to the break in a polymeric matrix with high transient time is lower than a matrix with lower transient time, but the load concentration factor in the matrix with high transient time is lower.

Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

  • Bae, Hwang;Kim, Dong Eok;Ryu, Sung-Uk;Yi, Sung-Jae;Park, Hyun-Sik
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.968-978
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    • 2017
  • Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal-hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.