• Title/Summary/Keyword: Creep-fatigue damage

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Study on Structural Characteristic for Durability Insurance of Turbopump Turbine (터보펌프 터빈의 내구성 확보를 위한 구조적 특성 연구)

  • Lee, Mu-Hyoung;Jang, Byung-Wook;Kwon, Jeong-Sik;Kim, Jin-Han;Jeong, Eun-Hwan;Jeon, Seong-Min;Lee, Soo-Yong;Park, Jung-Sun
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2009.11a
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    • pp.382-386
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    • 2009
  • The life of a component decreases when it was exposed at the extreme condition. A turbine blade of a turbopump used for a liquid rocket engine is operated under the environment of high temperature and pressure, and experienced high centrifugal force. Thus the durability of the turbopump operated under the these conditions become lower than expected because of the severe fatigue and creep influence. The damage of the turbine being considered the fatigue and the creep influence is estimated to ensure the durability of turbopump turbine. ABAQUS/CAE and MSC.Fatigue are used for the fatigue analysis, and Larson-Miller parameter and robinson's rule are used for the creep analysis. In this paper, comparison and analysis of the fatigue and the creep influence were performed to ensure the life expectancy of turbopump turbine.

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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.

Finite element analysis of inelastic thermal stress and damage estimation of Y-structure in liquid metal fast breeder reactor (액체금속로 Y-구조물의 비탄성 열응력 해석 및 손상평가에 관한 유한요소해석)

  • Kwak, D.Y.;Im, Y.T.;Kim, J.B.;Lee, H.Y.;Yoo, B.
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.7
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    • pp.1042-1049
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    • 1997
  • LMFBR(Liquid Metal Fast Breeder Reactor) vessel is operated under the high temperatures of 500-550.deg. C. Thus, transient thermal loads were severe enough to cause inelastic deformation due to creep-fatigue and plasticity. For reduction of such inelastic deformations, Y-piece structure in the form of a thermal sleeve is used in LMFBR vessel under repeated start-up, service and shut-down conditions. Therefore, a systematic method for inelastic analysis is needed for design of the Y-piece structure subjected to such loading conditions. In the present investigation, finite element analysis of heat transfer and inelastic thermal stress were carried out for the Y-piece structure in LMFBR vessel under service conditions. For such analysis, ABAQUS program was employed based on the elasto-plastic and Chaboche viscoplastic constitutive equations. Based on numerical data obtained from the analysis, creep-fatigue damage estimation according to ASME Code Case N-47 was made and compared to each other. Finally, it was found out that the numerical predictio of damage level due to creep based on Chaboche unified viscoplastic constitutive equation was relatively better compared to elasto-plastic constitutive formulation.

Elevated Temperature Design of KALIMER Reactor Internals Accounting for Creep and Stress-Rupture Effects

  • Koo, Gyeong-Hoi;Bong Yoo
    • Nuclear Engineering and Technology
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    • v.32 no.6
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    • pp.566-594
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    • 2000
  • In most LMFBR(Liquid Metal Fast Breed Reactor) design, the operating temperature is very high and the time-dependent creep and stress-rupture effects become so important in reactor structural design. Therefore, unlike with conventional PWR, the normal operating conditions can be basically dominant design loading because the hold time at elevated temperature condition is so long and enough to result in severe total creep ratcheting strains during total service lifetime. In this paper, elevated temperature design of the conceptually designed baffle annulus regions of KALIMER(Korea Advanced Liquid MEtal Reactor) reactor internal strictures is carried out for normal operating conditions which have the operating temperature 53$0^{\circ}C$ and the total service lifetime of 30 years. For the elevated temperature design of reactor internal structures, the ASME Code Case N-201-4 is used. Using this code, the time-dependent stress limits, the accumulated total inelastic strain during service lifetime, and the creep-fatigue damages are evaluated with the calculation results by the elastic analysis under conservative assumptions. The application procedures of elevated temperature design of the reactor internal structures using ASME Code Case N-201-4 with the elastic analysis method are described step by step in detail. This paper will be useful guide for actual application of elevated temperature design of various reactor types accounting for creep and stress-rupture effects.

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Evaluation of Creep-Fatigue Damage in 304 Stainless Steel using Ultrasonic Non-Destructive Test (초음파 비파괴 검사를 이용한 AISI 304 스테인리스강의 크리프-피로 손상의 평가)

  • Lee, Sung Sik;Oh, Yong Jun;Nam, Soo Woo
    • Korean Journal of Metals and Materials
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    • v.49 no.12
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    • pp.924-929
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    • 2011
  • It is well known that grain boundary cavitation is the main failure mechanism in austenitic stainless steel under tensile hold creep-fatigue interaction conditions. The cavities are nucleated at the grain boundary during cyclic loading and grow to become grain boundary cracks. The attenuation of ultrasound depends on scattering and absorption in polycrystalline materials. Scattering occurs when a propagation wave encounters microstructural discontinuities, such as internal voids or cavities. Since the density of the creep-fatigue cavities increases with the fatigue cycles, the attenuation of ultrasound will also be increased with the fatigue cycles and this attenuation can be detected nondestructively. In this study, it is found that individual grain boundary cavities are formed and grow up to about 100 cycles and then, these cavities coalesce to become cracks. The measured ultrasonic attenuation increased with the cycles up to cycle 100, where it reached a maximum value and then decreased with further cycles. These experimental measurements strongly indicate that the open pores of cavities contribute to the attenuation of ultrasonic waves. However, when the cavities develop, at the grain boundary cracks whose crack surfaces are in contact with each other, there is no longer any open space and the ultrasonic wave may propagate across the cracks. Therefore, the attenuation of ultrasonic waves will be decreased. This phenomenon of maximum attenuation is very important to judge the stage of grain boundary crack development, which is the indication of the dangerous stage of the structures.

Development of Web-based Design Compatibility Assessment Program for High Temperature Reactor (고온로 설계 적합성평가 프로그램 개발)

  • Cho, Doo Ho;Surh, Han Bum;Choi, Jae Boong;Huh, Nam Su;Choi, Young Hwan
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.9 no.1
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    • pp.48-55
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    • 2013
  • In this paper, W-DCAP-HTR(Web-based Design Compatibility Assessment Program for High Temperature Reactor) which will be used to check the design criteria for high temperature reactor is newly proposed. To do this, the assessment procedure of the ASME Sec.III Div.5 such as time-dependent primary stress limit, accumulated inelastic strain, and creep-fatigue damage evaluation were investigated. Furthermore, the trend of candidate materials for high temperature reactor was also reviewed. Then, all assessment procedures for high temperature reactor have been computerized to enhance the efficiency and to reduce the possibility of human error during calculating procedure by hand calculation. It can be directly conducted by adopting the actual thermal and structural analysis results. The validation of W-DCAP-HTR has been demonstrated by benchmark analysis.

A Fracture Mechanic Study on Life Prediction of Surface Cracks at Elevated Temperature (고온화 표면균열의 수명예측에 관한 파괴역학적 연구)

  • Chang-Min,Suh;Young-Ho,Kim;Bung-Ho,Son;Sang-Yeub,Oh
    • Bulletin of the Society of Naval Architects of Korea
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    • v.27 no.3
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    • pp.100-106
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    • 1990
  • Microcracking of type 304 stainless steel at $593^{\circ}C(1,100^{\circ}F)$ has been studied, in particular, initiation, growth, and coalescence of fatigue and creep microcracks on smooth specimens and small notch specimens via surface replicas and photomicrographs. Quantitative information, such as, initiation period, growth, and coalescence behavior, statistical distributions of crack length, density of cracks, distribution patterns and crack growth properties, were obtained. From this study, the fracture process, fatigue life, and creep life prediction characterized by the growth of surface microcracks have been analysed by a new approach unifying the conventional approaches based on the final fracture of materials with the fracture mechanics approach. Knowledge of these parameters is critical for the application of fracture mechanics to fatigue and creep life assessment, and the damage evaluation of structures at elevated temperature.

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A Study on Prediction of Crack growth Rate Under Creep-Fatigue Interaction (크리이프-피로 상호작용하의 균열성장속도 예측에 관한 연구)

  • Joo, Won-Sik;Cho, Seok-Swoo
    • Journal of Ocean Engineering and Technology
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    • v.9 no.2
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    • pp.98-111
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    • 1995
  • High temperature low cycle fatigue shows that cycle-dependent crack growth owing to cyclic plastic deformation occurred simultaneosly with time-dependent crack growth owing to intergranular deformation. Consequently, to estimate crack growth rate uniquely, many to investigators have proposed various kinds of parameters and theories but these could not produce satisfactory results. Therefore the goal of this study is focused on prediction of crack growth rate using predominant damage rule, linear cumulative damage rule and transitional parameter ${\Delta}J_c/{\Delta}J_f$. On the basis of these sinusoidal loading waveform at 600$^{\circ}C$ and 700$^{\circ}C$.

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Evaluation of Creep-Fatigue Integrity for High Temperature Pressure Vessel in a Sodium Test Loop (소듐 시험루프 내 고온 압력용기의 크리프-피로 건전성 평가)

  • Lee, Hyeong-Yeon;Lee, Dong-Won
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.38 no.8
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    • pp.831-836
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    • 2014
  • In this study, high temperature integrity evaluation on a pressure vessel of the expansion tank operating at elevated temperature of $510^{\circ}C$ in the sodium test facility of the SEFLA(Sodium Thermal-hydraulic Experiment Loop for Finned-tube Sodium-to-Air heat exchanger) to be constructed at KAERI has been performed. Evaluations of creep-fatigue damage based on a full 3D finite element analyses were conducted for the expansion tank according to the recent elevated temperature design codes of ASME Section III Subsection NH and French RCC-MRx. It was shown that the expansion tank maintains its integrity under the intended creep-fatigue loads. Quantitative code comparisons were conducted for the pressure vessel of austenitic stainless steel 316L.