• Title/Summary/Keyword: Fatigue Damage Evaluation

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Microstructural Evolution and Ultrasonic Nondestructive Evaluation During Creep-Fatigue of 9Cr Ferritic Heat-Resisting Steel (페라이트기 9Cr 내열강의 크리프-피로손상에 따른 미세조직 및 초음파 비파괴평가)

  • Kim, Chung-Seok;Kwun, S.I.;Park, Ik-Keun
    • Korean Journal of Materials Research
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    • v.17 no.8
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    • pp.425-432
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    • 2007
  • The microstructural evolution of ferritic 9Cr-1Mo-V-Nb steel, subjected to creep-fatigue at $550^{\circ}C$, was evaluated nondestructively by measuring the ultrasonic velocity. The variation of the ultrasonic velocity with the fatigue life fraction exhibited three regions. In the first region ($N/N_f$<0.2), a significant increase in the velocity was observed, followed by a slight increase between the fatigue life fractions of $0.2N_f$ and $0.8N_f$, and then a decrease in the final region. The change of the ultrasonic velocity during creep-fatigue was interpreted in relation to the microstructural properties. This study proposes an ultrasonic nondestructive evaluation method of quantifying the level of damage and microstructural change during the creep-fatigue of ferritic 9Cr-1Mo-V-Nb steel.

High-Temperature Design and Integrity Evaluation of Sodium-Cooled Fast Reactor Decay Heat Exchanger (소듐냉각고속로 붕괴열교환기의 고온 설계 및 건전성 평가)

  • Lee, Hyeong-Yeon;Eoh, Jae-Hyuk
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.10
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    • pp.1251-1259
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    • 2013
  • In this study, high temperature design and creep-fatigue damage evaluation of a decay heat exchanger (DHX) in the decay heat removal systems of a sodium-cooled fast reactor (SFR) have been performed. Detail design and 3D finite element analysis have been conducted for the DHXs to be installed in active and passive decay heat removal systems in Korean Generation IV SFR, and the DHX installed in the STELLA-1(Sodium integral effect test loop for safety simulation and assessment) at KAERI (Korea Atomic Energy Research Institute). Evaluations of creep-fatigue damage based on full 3D finite element analyses were conducted for the two Mod.9Cr-1Mo steel heat exchangers according to the elevated temperature design codes of ASME Section III Subsection NH and RCC-MR code. Code comparisons were made based on the creep-fatigue damage evaluation and issues on conservatisms of the design codes were discussed.

Fatigue Life Prediction and Strength Evaluation of Shot Peened Parts (쇼트피이닝한 부재의 피로수명 예측 및 피로강도 평가)

  • Kim, Hwan-Du;Lee, Sun-Bok
    • 한국기계연구소 소보
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    • s.15
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    • pp.75-87
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    • 1985
  • A review was performed on fatigue life prediction and strength evaluation of shot peened parts. Fatigue strength of machine parts can be improved by shot peening due to compressive residual stresses on such parts. Compressive residual stress cannot be uniquely define by peening intensity. Several measuring methods of residual stress and the principle of hole drilling method are presented. Exploratory measurement of residual stress was performed on the shot peened SM35C plate with the hole drilling method. Fatigue life and failure location of shot peened parts under bending load can be predicted by a damage parameter which is incorporated with material properties, residual stress, and applied stress conditions. Some method are presented to predict the fatigue strength of shot peened parts at any given life. Shot peening gives its full benefit to the notched machine parts of high strength steels.

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Development of Material Properties Measurement and Fatigue Life Evaluation System (재료물성치 측정 및 피로수명평가 시스템의 개발)

  • 박종주;서상민;최용식;김영진
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.18 no.6
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    • pp.1465-1473
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    • 1994
  • This paper describes the development strategy and contents of a fatigue life evaluation system, FLEVA. The system is composed of 4 parts; material properties, load histories, cycle counting and life prediction. The cycle counting is based on the rain-flow counting method and peak counting method, and the life prediction is performed based on the linear damage rule. Material properties(static, fatigue) are also provided as a database obtained by a computer aided test system. Case study is performed to verify the developed program.

Fatigue Life Evaluation of Motor Block Bracket Units for KTX-Sancheon Trains (KTX-산천 열차용 모터 감속기 고정대의 피로 수명 평가)

  • Lee, Chan-Woo;Lee, Dong-Hyong
    • Journal of the Korean Society for Precision Engineering
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    • v.29 no.6
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    • pp.626-631
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    • 2012
  • In this study, fatigue life of the motor block bracket units for KTX-Sancheon trains was assessed. Design evaluation for railway structures was performed based on the UIC 566 regulation, and test and evaluation of fatigue life in welded parts was performed in accordance with standard ERRI B 12/RP17 and ERRI B 12/RP60. The actual vehicle dynamic stress testing was executed in KTX-Sancheon service line with the service operating speed. The dynamic stress was measured with commercial data acquisition system (MGC plus). The cumulative damage was evaluated by applying standard BS 7608 - Class F and cycle counting was used rain-flow counting method. As a result, the motor block bracket units for KTX-Sancheon trains was designed to fit the regulation and the safety of fatigue life for 30 years, assuming that KTX-Sancheon trains travels 600,000km annually, were confirmed under current operating conditions.

Current Status on the Development and Application of Fatigue Monitoring System for Nuclear Power Plants (원전 피로 감시 시스템 개발 및 적용 현황)

  • Boo, Myung Hwan;Lee, Kyoung Soo;Oh, Chang Kyun;Kim, Hyun Su
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.13 no.2
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    • pp.1-18
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    • 2017
  • Metal fatigue is an important aging mechanism that material characteristics can be deteriorated when even a small load is applied repeatedly. An accurate fatigue evaluation is very important for component structural integrity and reliability. In the design stage of a nuclear power plant, the fatigue evaluations of the Class 1 components have to be performed. However, operating experience shows that the design evaluation can be very conservative due to conservatism in the transient severity and number of occurrence. Therefore, the fatigue monitoring system has been considered as a practical mean to ensure safe operation of the nuclear power plants. The fatigue monitoring system can quantify accumulated fatigue damage up to date for various plant conditions. The purpose of this paper is to describe the fatigue monitoring procedure and to introduce the fatigue monitoring program developed by the authors. The feasibility of the fatigue monitoring program is demonstrated by comparing with the actual operating data and finite element analysis results.

Life Evaluation of Gas Turbine Engine Disk based on Retirement for Cause Concept (Retirement For Cause 개념에 의한 가스터빈 디스크 수명의 평가)

  • Nam, Seung-Hun;Park, Jong-Hwa;Kim, Jong-Yeop
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.2
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    • pp.365-373
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    • 2002
  • For gas turbine engines, the safe life methodology has historically been used fur fatigue life management of failure critical engine components. The safe retirement limit is necessarily determined by a conservative life evaluation procedure, thereby many components which have a long residual life are discarded. The objective of this study is to introduce the damage tolerant design concept into the life management for aircraft engine component instead of conservative fatigue life methodology which has been used for both design and maintenance. Crack growth data were collected on a nickel base superalloy which have been subjected to combined static and cyclic loading at elevated temperatures. Stress analysis fur turbine disk was carried out. The program for computing creep-fatigue crack growth was developed. The residual lifes of turbine disk component under various temperatures and conditions using creep-fatigue crack growth data were estimated. As the result of analysis, it was confirmed that retirement fur cause concept was applicable to the evaluation of residual life of retired turbine disk which had been designed based on the conventional fatigue life methodology.

Assessment of Fatigue and Fracture on a Tee-Junction of LMFBR Piping Under Thermal Striping Phenomenon

  • Lee, Hyeong-Yeon;Kim, Jong-Bum;Bong Yoo
    • Nuclear Engineering and Technology
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    • v.31 no.3
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    • pp.267-275
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    • 1999
  • This paper deals with the industrial problem of thermal striping damage on the French prototype fast breeder reactor, Phenix and it was studied in coordination with the research program of IAEA. The thermomechanical and fracture mechanics evaluation procedure of thermal striping damage on the tee-junction of the secondary piping using Green's function method and standard FEM is presented. The thermohydraulic(T/H) loading condition used in the present analysis is the random type thermal loads computed by T/H analysis on the turbulent mixing of the two flows with different temperatures. The thermomechanical fatigue damage was evaluated according to ASME code section 111 subsection NH. The results of the fatigue analysis showed that fatigue failure would occur at the welded joint within 90,000 hours of operation. The assessment for the fracture behavior of the welded joint showed that the crack would be initiated at an early stage in the operation. It took 42,698.9 hours for the crack to propagate up to 5 mm along the thickness direction. After then, however, the instability analysis, using tearing modulus, showed that the crack would be arrested, which was in agreement with the actual observation of the crack. An efficient analysis procedure using Green's function approach for the crack propagation problem under random type load was proposed in this study. The analysis results showed good agreement with those of the practical observations.

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Simulation of Extremely Low Cycle Fatigue Fracture in Ductile Cast Iron (구상흑연주철 극저사이클 피로파괴의 시뮬레이션 구현)

  • Kim, Min-Gun;Lim, Bok-Kyu
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.30 no.12 s.255
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    • pp.1573-1580
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    • 2006
  • In this study, fatigue tests were carried out under push-pull loading condition using spheroidal graphite cast iron in order to clarify the internal fatigue fracture mechanism in an extremely low cycle fatigue regime. It is found that a successive observation of internal fatigue damage it is found that the fracture processes go through three stages, that is, the generation, growth and coalescence of microvoids originated from debonding of graphite-matrix interface. It is also found that the crack which is initiated from the void propagates by coalescence of neighboring cracks and the fatigue crack growth rate can be expressed in form of the Manson-Coffin rule type. In this paper, quantitative analyses of fatigue properties for realization of simulation about fatigue life evaluation are also presented.

The Evaluation of the Stress Corrosion Cracking for Improvement of Reliability in Turbine Operation and Maintenance (터빈 운전 신뢰성 향상을 위한 응력부식균열 평가)

  • Kang, Yong-Ho;Song, Jung-Il
    • 한국태양에너지학회:학술대회논문집
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    • 2008.11a
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    • pp.280-287
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    • 2008
  • In case of low pressure steam turbine used in power plant, it was operated in wet steam and high stress condition. Therefore, it is possible that the corrosion damage of low pressure was induced by this condition. According to previous study, about 30% of total blade failure correspond to corrosion fatigue or SCC(stress corrosion cracking) in low pressure turbine. Especially, LSB(last stage bucket) of low pressure turbine has a higher hardness to prevent erosion damage due to water droplet however, generally this is more dangerous for SCC damage. Therefore, to improve reliability of turbine blade. various methods for SCC evaluation has been developed. In this study, the crack found in LSB during in-service inspection was evaluated using microstructure analysis and stress analysis. From the stress analysis, the optimum size of fillet to remove the crack was proposed. And also, the reliability was evaluated for modified LSB using GOODMAN diagram.

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