• Title/Summary/Keyword: Mechanical stress analysis

Search Result 3,814, Processing Time 0.038 seconds

Thermal stress intensity factor solutions for reactor pressure vessel nozzles

  • Jeong, Si-Hwa;Chung, Kyung-Seok;Ma, Wan-Jun;Yang, Jun-Seog;Choi, Jae-Boong;Kim, Moon Ki
    • Nuclear Engineering and Technology
    • /
    • v.54 no.6
    • /
    • pp.2188-2197
    • /
    • 2022
  • To ensure the safety margin of a reactor pressure vessel (RPV) under normal operating conditions, it is regulated through the pressure-temperature (P-T) limit curve. The stress intensity factor (SIF) obtained by the internal pressure and thermal load should be obtained through crack analysis of the nozzle corner crack in advance to generate the P-T limit curve for the nozzle. In the ASME code Section XI, Appendix G, the SIF via the internal pressure for the nozzle corner crack is expressed as a function of the cooling or heating rate, and the wall thickness, however, the SIF via the thermal load is presented as a polynomial format based on the stress linearization analysis results. Inevitably, the SIF can only be obtained through finite element (FE) analysis. In this paper, simple prediction equations of the SIF via the thermal load under, cool-down and heat-up conditions are presented. For the Korean standard nuclear power plant, three geometric variables were set and 72 cases of RPV models were made, and then the heat transfer analysis and thermal stress analysis were performed sequentially. Based on the FE results, simple engineering solutions predicting the value of thermal SIF under cool-down and heat-up conditions are suggested.

Effect of Normal Operating Condition Analysis Method for Weld Residual Stress of CRDM Nozzle in Reactor Pressure Vessel (원전 정상가동조건 적용 방식이 원자로 압력용기 상부헤드 관통 노즐의 용접 잔류응력에 미치는 영향)

  • Nam, Hyun Suk;Bae, Hong Yeol;Oh, Chang Young;Kim, Ji Soo;Kim, Yun Jae
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.37 no.9
    • /
    • pp.1159-1168
    • /
    • 2013
  • In pressurized water nuclear reactors (PWRs), the reactor pressure vessel (RPV) upper head contains penetration nozzles that use a control rod drive mechanism (CRDM). The penetration nozzle uses J-groove weld geometry. Recently, the occurrence of cracking in alloy 600 CRDM penetration nozzle has increased. This is attributable to primary water stress corrosion cracking (PWSCC). PWSCC is known to be susceptible to the welding residual stress and operational stress. Generally, the tensile residual stress is the main factor contributing to crack growth. Therefore, this study investigates the effect on weld residual stress through different analysis methods for normal operating conditions using finite element analysis. In addition, this study also considers the effect of repeated normal operating condition cycles on the weld residual stress. Based on the analysis result, this paper presents a normal operating condition analysis method.

Influence of Inclined Holes in Measurement of Residual Stress by the Hole Drilling Method

  • Kim, Cheol;Yang, Won-Ho;Heo, Sung-Pil
    • Journal of Mechanical Science and Technology
    • /
    • v.15 no.12
    • /
    • pp.1647-1654
    • /
    • 2001
  • The hole drilling method is widely used in measuring residual stress in surfaces. In this method, the inclination of holes is one of the sources of error. This paper presents a finite element analysis of the influence of inclined holes on the uniaxial residual stress field. The error in stress has been found to increase proportionally to the correct inclined angle of the hole. The correction equations by which one may easily obtain the residual stress, taking account of the inclined angle and direction, have been derived. The error of stress due to the inclined hole has been reduced to around 1% using the correction equations.

  • PDF

Stress Analysis of the GEO-KOMPSAT-2 Tubing System (정지궤도복합위성 추진계 배관망 구조해석)

  • Jeong, Gyu;Lim, Jae Hyuk;Chae, Jongwon;Jeon, Hyung-Yoll
    • Journal of Aerospace System Engineering
    • /
    • v.12 no.1
    • /
    • pp.47-56
    • /
    • 2018
  • In this paper, the structural analysis of the Geostationary Korea Multi-Purpose Satellite-2 (GEO-KOMPSAT-2) tubing system is discussed, and the structural integrity of the tubing system is assessed by comparative analysis with the results of overseas partner AIRBUS. Securing structural reliability of the tubing system is a very important key element of the propulsion system of the GEO-KOMPSAT-2 satellite. Therefore, FE modeling of the propulsion tubing was carried out directly using the CAE program, and structural analysis was performed to evaluate the stress state under launch conditions. Hoop stress, axial stress, bending stress, and torsion stress were calculated according to diverse load conditions by using pressure stress analysis, thruster alignment analysis, sine qualification load analysis, and random qualification load analysis. From the results, the Margin of Safety (MoS) of the tubing system is evaluated, and we can verify the structural integrity of the tubing system when subjected to various launch loads.

Thermal Stress Analysis of Functuonally Graded Ceramic/Metal Composites(II) (경사기능성 세라믹/금속 복합재료의 열응력해석)

  • Lim, Jae-Kyoo;Song, Jun-Hee
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.21 no.10
    • /
    • pp.1571-1579
    • /
    • 1997
  • The development of a new material which should be continuously use under severe environment of very high temperature has been urgently requested. For the development of such super-heat resistant materials, the main problem is not only to make the superior thermal barrier properties but also to actively release thermal stress. So, a new concept of functionally graded material(FGM) has been proposed to overcome this problem. A composition and microstructure of FGM are varied continuously from place to place in ways designed to provide it with the maximum function of mitigating the induced thermal stress. So, FGM can be applied in the aerospace, the electronic and the medical field, etc.. In this study, thermal stress analysis of sintering PSZ/NiCrAlY graded material was conducted theoretically using a finite-element program. The temperature condition was sintering temperature assuming a cooling-down process up to room temperature. Fracture damage mechanism was anlayzed by the parameters of residual stress. It could be known that FGM provided with the function of mitigating the induced thermal stress.

Analysis of Mechanical Stress Due to Magnetic Force and Thermal Expansion in Brsushless Motor (브러시레스 전동기에서 전자기적 가진력 및 열에 의한 기계적 음력해석)

  • Ha, Gyeong-Ho;Hong, Jeong-Pyo;Lee, Geun-Ho
    • The Transactions of the Korean Institute of Electrical Engineers B
    • /
    • v.51 no.5
    • /
    • pp.221-227
    • /
    • 2002
  • This paper deals with the mechanical stress analysis due to electromagnetic forces and the optimal design of the link considering the stress. The link in Interior Permanent Magnet Brushless Motor(IPM) have influence on both mechanical and magnetic performance. The decrease of the link thickness serves to improve the torque, whereas this decreases the strength of link. Therefore, it is necessary to determine the appropriate link thickness considering electromagnetic forces and thermal expansion. The effects of the variation of link thickness on the mechanical stress and the electromagnetic performance are analyzed by the structural and electromagnetic Finite Element Method. In addition, the mechanical structure design of the link is performed to reinforce the mechanical strength against magnetic forces while preserving a food magnetic torque.

Analysis of a Conducting Crack in an Electrostrictive Ceramic Under Combined Electric and Mechanical Loading

  • Beom, Hyeon-Gyu;Jeong, Kyoung-Moon;Jeong, Eun-Do
    • Journal of Mechanical Science and Technology
    • /
    • v.16 no.8
    • /
    • pp.1117-1126
    • /
    • 2002
  • A conducting crack in an electrostrictive ceramic under combined electric and mechanical loading is investigated. Analysis based on linear dielectric model predicts that the surfaces of the crack are not open completely but they are contact near the crack tip. The complete solution for the crack with a contact zone in a linear electrostrictive ceramic under combined electric and mechanical loading is obtained by using the complex variable formula. The asymptotic problems for a semi-infinite crack with a partial opening zone as well as for a fully open semi-infinite crack in a nonlinear electrostrictive ceramic are analyzed in order to investigate the effect of the electrical nonlinearity on the stress intensity factor under small scale nonlinear conditions. Particular attention is devoted to a finite crack in the nonlinear electrostrictive ceramic subjected to combined electric and mechanical loading. The stress intensity factor for the finite crack under small scale nonlinear conditions is obtained from the asymptotic analysis.

Stress evaluation method of reinforced wall-thinned Class 2/3 nuclear pipes for structural integrity assessment

  • Jae-Yoon Kim;Je-Hoon Jang;Jin-Ha Hwang;Yun-Jae Kim
    • Nuclear Engineering and Technology
    • /
    • v.56 no.4
    • /
    • pp.1320-1329
    • /
    • 2024
  • When wall-thinning occurs in nuclear Class 2 and 3 pipes, reinforcement is typically applied rather than replacement. To analyze the structural integrity of reinforced wall-thinned pipe, stress analysis results using full 3-D FE analysis are not compatible to the design code equation, ASME BPVC Sec. III NC/ND-3650. Therefore, the efficient stress evaluation method for the reinforced wall-thinned pipe, compatible to the design code equation, needs to be developed. In this paper, stress evaluation methods for the reinforced wall-thinned pipe are proposed using the equivalent straight pipe concept. Furthermore, for fatigue analysis of the reinforced wall-thinned pipe, the stress intensification factor of reinforced wall-thinned pipe is presented using the structural stress method given in ASME BPVC Sec. VIII Div.2.

A Study on Stress Distribution of Korean High Speed Train Wheel at Tread Braking (한국형 고속전철의 답면제동에 의한 차륜의 응력분포에 관한 연구)

  • 권범진;정흥채;김호경
    • Journal of the Korean Society for Railway
    • /
    • v.5 no.3
    • /
    • pp.167-173
    • /
    • 2002
  • The influence of thermal stress at tread breaking in Korean High Speed Train wheel was investigated using the coupled thermal-mechanical analysis technique. The mechanical load or wheel-rail contract load and braking load were considered during FEM analysis. During the stop braking, the effect of mechanical stress on the combined stress is relatively larger than that of thermal stress in the rim of wheel. However, the effect of thermal stress is relatively larger than that of mechanical stress in the plate of wheel. When 300% of the block force was applied, the maximum von Mises stress of 61.0 MPa was found at the outside plate around 400 mm far away from the wheel center.

Approximate residual stress and plastic strain profiles for laser-peened alloy 600 surfaces

  • Eui-Kyun Park ;Hyun-Jae Lee ;Ju-Hee Kim ;Yun-Jae Kim
    • Nuclear Engineering and Technology
    • /
    • v.55 no.4
    • /
    • pp.1250-1264
    • /
    • 2023
  • This paper presents approximate in-depth residual stress and plastic strain profiles for laser-peened alloy 600 surface via FE analysis. In approximations, effects of the initial welding residual stress and the number of shots are quantified. Based on FE analysis results, residual stress profiles are quantified by two variables; the maximum difference in stress before and after LSP, and the depth up to which the compressive residual stress exists. Plastic strain profiles are quantified by one variable, the maximum equivalent plastic strain at the surface. The proposed profiles are validated by comparing with published LSP experimental results for welded plates. Effects of the initial welding residual stress and the number of shots on these variables are discussed. The proposed profile can be directly applied to predict the mitigation effect of LSP on PWSCC and to efficiently perform structural integrity assessment of laser peened nuclear components.