• 제목/요약/키워드: thermal stresses

검색결과 832건 처리시간 0.025초

기계적 응력이완 방법에 의한 원전기기 용접부의 잔류응력 재분포 (Residual Stress Redistribution on Welds of Nuclear Component by Mechanical Stress Relieving Methods)

  • 이세환;김종성;진태은
    • Journal of Welding and Joining
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    • 제22권2호
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    • pp.51-58
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    • 2004
  • Residual stresses, which can be produced during the welding process, play an important role in an industrial field. Welding residual stresses are exerting negative effect on the fatigue behavior and integrity of structure. In this study, as a result of the thermal elasto-plastic finite element analysis for the welds of a nuclear component, the residual stress distributions are estimated for as-welded condition. Also, finite element techniques are developed to simulate the relaxation of the residual stresses according to the various mechanical stress relieving(MSR) loads such as hydrostatic pressure loading, tensile pipe-end loading, and mechanical stress improvement process(MSIP) loading. Finally, the results of residual stress redistributions for various loading conditions are compared and reviewed qualitatively and quantitatively to find an optimum loading condition.

레일의 제조공정에서 비금속 개재물에 의한 레일의 잔류응력 해석 (Analysis of the Residual Stress Produced by non-metallic Inclusions during Rail Manufacturing Process)

  • 구병춘;정우현;이희성;서정원
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 1999년도 춘계학술대회 논문집
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    • pp.352-357
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    • 1999
  • During the cooling process of rail, residual stresses are produced due to the difference of the coefficients of thermal expansion between rail and inhomogeneous non-metallic inclusions such as sulphides and oxides. A micro-mechanical approach is used to obtain the stresses in the inclusions and matrix, After obtaining the stress of an elliptical inhomogeneous inclusion in an infinite domain, average stresses of randomly distributed spherical inclusions are obtained by use of Mori-Tanaka's self consistent method. The magnitude of the calculated residual stress is near to the yield stress of the matrix in case of the spherical inclusions.

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국부변형률방법을 이용한 용접시험편의 피로수명 해석 (Fatigue Life Analysis of Butt-welded specimen by Local Strain Approach)

  • 이동형;서정원;구병춘;석창성
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2003년도 추계학술대회 논문집(III)
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    • pp.73-78
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    • 2003
  • The residual stresses and. distortions of structures by welding exert negative effect on the safety of railroad structures. This investigation performs a thermal elasto-plastic analysis using finite element techniques to evaluate residual stresses in butted-welded joint. Considering this initial residual stresses, local stress and strain at the critical location (weld toe) during the loading were analyzed by elastic plastic finite element analysis. Fatigue crack initiation life and fatigue crack propagation life of butt-welded specimen were predicted by local strain approach and Neuber's role and Paris law. It is demonstrated that fatigue life estimates by local strain approach closely approximate the experimental results.

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Analysis of Hygrothermal Stresses in a Viscoelastic Thin Film

  • Lee, Sang-Sun
    • 한국반도체및디스플레이장비학회:학술대회논문집
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    • 한국반도체및디스플레이장비학회 2003년도 추계학술대회 발표 논문집
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    • pp.146-153
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    • 2003
  • This paper deals with the stress singularity induced at the interface corner between the viscoelastic thin film and the rigid substrate subjected to the combined influence of temperature change and moisture absorption. A boundary element analysis is employed to investigate the behavior of interface stresses. The film is assumed to be thermorheologically simple. It is further assumed that moisture effects are analogous to thermal effects. Numerical results are presented for a given viscoelastic model, indicating the singular residual stresses induced during cooling down from the curing temperature, and how they can be altered by subsequent moisture absorption at room temperature.

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수화열에 의한 균열 저감 공법에 관한 연구 (Development of Reduction Methods of Thermal Stresses Due to Hydration Heat)

  • 양주경
    • 한국산학기술학회논문지
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    • 제9권6호
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    • pp.1705-1710
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    • 2008
  • 본 연구에서는 외기 온도의 변화를 반영하여 수화열에 의한 열전달 및 열응력 해석이 가능한 프로그램을 개발하고, 재료적 측면에서 수화열에 의한 균열 발생 가능성을 최소화하기 위하여 제5종포틀랜드시멘트를 사용하는 경우, 제5종포틀랜드시멘트와 플라이애쉬를 같이 사용하는 경우, 제5종포틀랜드시멘트와 강섬유를 같이 사용하는 경우를 실험하여 비교 검토하였다. 플라이애쉬를 대체하여 사용하면 콘크리트의 최고 온도를 낮추는 효과를 기대할 수 있지만, 인장응력의 감소 효과는 온도의 감소 효과만큼 크게 나타나지 않았다. 또한 강섬유를 혼입하여 사용하면 온도 및 인장응력의 저감 측면에서 매우 효과적인 것으로 나타났다.

Influence of temperature on the beams behavior strengthened by bonded composite plates

  • Bouazza, Mokhtar;Antar, Kamel;Amara, Khaled;Benyoucef, Samir;Bedia, El Abbes Adda
    • Geomechanics and Engineering
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    • 제18권5호
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    • pp.555-566
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    • 2019
  • The purpose of this paper is to investigate the thermal effects on the behaviour reinforced-concrete beams strengthened by bonded angle-ply laminated composites laminates plate $[{\pm}{\theta}n/90m]_S$. Effects of number of $90^{\circ}$ layers and number of ${\pm}{\theta}$ layers on the distributions of interfacial stress in concrete beams reinforced with composite plates have also been studied. The present results represent a simple theoretical model to estimate shear and normal stresses. The effects the temperature, mechanical properties of the fibre orientation angle of the outer layers, the number of cross-ply layers, plate length of the strengthened beam region and adhesive layer thickness on the interfacial shear and normal stresses are investigated and discussed.

Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor

  • Ma, Yugao;Liu, Jiusong;Yu, Hongxing;Tian, Changqing;Huang, Shanfang;Deng, Jian;Chai, Xiaoming;Liu, Yu;He, Xiaoqiang
    • Nuclear Engineering and Technology
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    • 제54권6호
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    • pp.2094-2106
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    • 2022
  • The solid-state core of a heat pipe cooled reactor operates at high temperatures over 1000 K with thermal and irradiation-induced expansion during burnup. The expansion changes the gap thickness between the solid components and the material properties, and may even cause the gap closure, which then significantly influences the thermal and mechanical characteristics of the reactor core. This study developed an irradiation behavior model for HPRTRAN, a heat pipe reactor system analysis code, to introduce the irradiation effects such as swelling and creep. The megawatt heat pipe reactor MegaPower was chosen as an application case. The coupled irradiation-thermal-mechanical model was developed to simulate the irradiation effects on the heat transfer and stresses of the whole reactor core. The results show that the irradiation deformation effect is significant, with the irradiation-induced strains up to 2.82% for fuel and 0.30% for monolith at the end of the reactor lifetime. The peak temperatures during the lifetime are 1027:3 K for the fuel and 956:2 K for monolith. The gap closure enhances the heat transfer but caused high stresses exceeding the yield strength in the monolith.

Thermal-Mixing Analyses for Safety Injection at Partial Loop Stagnation of a Nuclear Power Plant

  • Hwang, Kyung-Mo;Kim, Kyung-Hoon
    • Journal of Mechanical Science and Technology
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    • 제17권9호
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    • pp.1380-1387
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    • 2003
  • When a cold HPSI (High pressure Safety Injection) fluid associated with an overcooling transient, such as SGTR (Steam Generator Tube Rupture), MSLB (Main Steam Line Break) etc., enters the cold legs of a stagnated primary coolant loop, thermal stratification phenomena will arise due to incomplete mixing. If the stratified flow enters the downcomer of the reactor pressure vessel, severe thermal stresses are created in a radiation embrittled vessel wall by local overcooling. As general thermal-hydraulic system analysis codes cannot properly predict the thermal stratification phenomena, RG 1.154 requires that a detailed thermal-mixing analysis of PTS (pressurized Thermal Shock) evaluation be performed. Also. previous PTS studies have assumed that the thermal stratification phenomena generated in the stagnated loop side of a partially stagnated primary coolant loop are neutralized in the vessel downcomer by the strong flow from the unstagnated loop. On the basis of these reasons, this paper focuses on the development of a 3-dimensional thermal-mixing analysis model using PHOENICS code which can be applied to both partial and total loop stagnated cases. In addition, this paper verifies the fact that, for partial loop stagnated cases, the cold plume generated in the vessel downcomer due to the thermal stratification phenomena of the stagnated loop is almost neutralized by the strong flow of the unstagnated loop but is not fully eliminated.

고온 수직형 압력용기 Skirt 부의 열응력에 관한 연구 (Thermal Stress at the Junction of Skirt to Head in Hot Pressure Vessel)

  • 한명수;한종만;조용관
    • Journal of Welding and Joining
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    • 제16권2호
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    • pp.111-121
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    • 1998
  • It is well recognized that a excessive temperature gradient from the junction of head to skirt in axial direction in a hot pressure vessel can cause unpredicted high thermal stress at the junction and/or in axial direction of a skirt. this thermal stress resulting from axial thermal gradient may be a major cause of unsoundness of structural integrity. In case of cyclic operation of hot pressure vessels, the thermal stress becomes one of the primary design consideration because of the possibility of fracture as a result of cyclic thermal fatigue and progressively incremental plastic deformation. To perform thermal stress analysis of the junction and cylindrical skirt of a vessel, or, at least, to inspect quantitatively the magnitude and effect of thermal stress, the temperature profile of the vessel and skirt must be known. This paper demonstrated the temperature distribution and thermal stress analysis for the junction of skirt to head using F.E. analysis. Effect of air pocket in crotch space was quantitatively investigated to minimize the temperature gradient causing the thermal stress in axial direction. Effect of the skirt height on thermal stresses was also studied. Analysis results were compared with theoretical formulas to verify th applicability to the strength calculation in design field.

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경사기능층의 디자인에 의한 열응력분산재료 합성에 관한 연구 (Synthesis of the material releasing thermal stress by designing FGM)

  • 김유택;박진호
    • 한국결정성장학회지
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    • 제9권2호
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    • pp.240-244
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    • 1999
  • 화학기상증착법(CVD)을 사용하여 graphite 기판 위에 단층의 SiC와 SiC/C 경사기능층을 증착시켰다. 먼저 상업적인 전산 구조 해석 프로그램을 사용하여 열충격하에 있는 재료층 내부의 온도 분포 및 열응력 분포를 계산하였고, 계산에 의해 설계, 제작된 경사기능층 시편들의 열특성을 조사하였다. 열충격 시험결과, 경사기능층 시편들이 계면에서 매우 효율적인 열응력 이완특성을 나타내는 것을 알 수 있었고, $\Delta$T=1600K의 열충격에도 변형이 없음을 알 수 있었다.

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