• Title/Summary/Keyword: 잔류응력 분포

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Analysis of Stress Singularity on Ceramics/Metal Bonded Joints (세라믹/금속 접합재에 대한 응력특이성의 해석)

  • Kim, Ki-Seong;Kim, Hui-Song;Chung, Nam-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.20 no.10
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    • pp.3058-3067
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    • 1996
  • With increasing use of ceramics/metal bonded joints, It is required to analyze the residual stress distribution and stress singularity at an interface edge for its bonded joints. In this paper, the residual stress distribution and stress singularity index of the ceramics/metal bonded joints were analyzed by using 2-dimensional elastic boundary element method. The variations of residual stress distribution and stress singularity index are studied with changes for the combinations of ceramics/metal bodned joints.

Sensitivity Analysis of Nozzle Geometry Variables for Estimating Residual Stress in RPV CRDM Penetration Nozzle (원자로 상부헤드 관통노즐의 잔류응력 예측을 위한 노즐 형상 변수 민감도 연구)

  • Bae, Hong Yeol;Oh, Chang Young;Kim, Yun Jae;Kim, Kwon Hee;Chae, Soo Won;Kim, Ju Hee
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.3
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    • pp.387-395
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    • 2013
  • Recently, several circumferential cracks were found in the control rod drive mechanism (CRDM) nozzles of U.S. nuclear power plants. According to the accident analyses, coolant leaks were caused by primary water stress corrosion cracking (PWSCC). The tensile residual stresses caused by welding, corrosion sensitive materials, and boric acid solution cause PWSCC. Therefore, an exact estimation of the residual stress is important for reliable operation. In this study, finite element simulations were conducted to investigate the effects of the tube geometry (thickness and radius) on the residual stresses in a J-groove weld for different CRDM tube locations. Two different tube locations were considered (center-hole and steepest side hill tube), and the tube radius and thickness variables ($r_o/t$=2, 3, 4) included two different reference values ($r_o$=51.6, t=16.9mm).

Effects of Repair Weld of Reactor Pressure Vessel Upper Head Control Rod Drive Mechanism Penetration Nozzle on J-Groove Weldment Using Finite Element Analysis (유한요소법을 이용한 원자로 상부헤드 CRDM 관통노즐 J-Groove 보수용접 영향 분석)

  • Kim, Ju Hee;Yoo, Sam Hyeon;Kim, Yun Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.38 no.6
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    • pp.637-647
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    • 2014
  • In pressurized water reactors, the upper head of the reactor pressure vessel (RPV) contains numerous control rod drive mechanism (CRDM) nozzles. These nozzles are fabricated by welding after being inserted into the RPV head with a room temperature shrink fit. The tensile residual stresses caused by this welding are a major factor in primary water stress corrosion cracking (PWSCC). Over the last 15 years, the incidences of cracking in alloy 600 CRDM nozzles have increased significantly. These cracks are caused by PWSCC and have been shown to be driven by the welding residual stresses and operational stresses in the weld region. Various measures are being sought to overcome these problems. The defects resulting from the welding process are often the cause of PWSCC acceleration. Therefore, any weld defects found in the RPV manufacturing process are immediately repaired by repair welding. Detailed finite-element simulations for the Korea Nuclear Reactor Pressure Vessel were conducted in order to predict the magnitudes of the repair weld residual stresses in the tube materials.

Influence of residual stress due to shot peening on fatigue strength and life (피로강도 및 수명에 미치는 Shot Peening에 의한 잔류응력의 영향)

  • Lee, Jong-Gyu;Kim, Jeong-Gyu
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.9
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    • pp.1498-1506
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    • 1997
  • Procedures are presented for influence of shot peening on fatigue strength, fatigue life and effects of shot peening are discussed from experiments were taken between shot peened and unpeened SPS5, SM45C specimens. After the residual stress on shot peened specimens was measured by X-ray diffractometer, rotating bending fatigue tests were carried out. In addition, the compressive residual stress profile was obtained by the superposition method of three stresses which is based on Al-Obaid's equation. Predicted fatigue life considering residual stress profile which was obtained by the Al-Obaid's equation and another predicted fatigue life considering residual stress profile which was measured in test were compared. For the purpose of predicting fatigue life, Morrow's equation considering the residual stress and mean stress was used.

2.25Cr-1Mo 강에 대한 Laser 및 SMAW 용접부의 잔류응력 분포 및 특성 비교

  • Bang, Han-Sur;Kim, Young-Pyo;Kim, Kun-Sung;Kim, Hyoung
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2003.10a
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    • pp.97-99
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    • 2003
  • In order to confirm the possibility of application of laser welding process to 2.25Cr-1Mo steel, the characteristic of residual stress distribution in welds by SMAW and $CO_{2}$ Laser welding process have been investigated and compared using the numerical analysis. As the Result of the numerical analysis, the possibility of application of laser welding process has been found out in respect to the welding residual stress distribution and mechanical properties in welds.

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Effect of preemptive weld overlay sequence on residual stress distribution for dissimilar metal weld of Kori nuclear power plant pressurizer (고리 원전 가압기 PWOL의 용접 방향이 이종금속용접부 잔류응력 분포에 미치는 영향)

  • Bae, H.Y.;Song, T.K.;Chun, Y.B.;Oh, C.Y.;Kim, Y.J.;Lee, K.S.;Park, C.Y.
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.88-93
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    • 2008
  • Weld overlay is one of the residual stress mitigation method which arrest crack. An overlay weld sued in this manner is termed a preemptive weld overlay(PWOL). PWOL was good for distribution of residual stress of dissimilar metal weld(DMW) by previous research. Because range of overlay welding is wide relatively, residual stress distribution on PWR is affected by welding sequence. In order to examine the effect of welding sequence, PWOL was applied to a specific DMW of KORI nuclear power plant by finite element analysis method. As a result, the welding direction that from nozzle to pipe is better good for residual stress distribution on PWR.

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