• Journal of Welding and Joining
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• v.17 no.4
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• pp.76-84
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• 1999

The residual stress generated when the steel plates were produced, did not influence on the out-of-plane deformation and residual stress generated by welding. When the initial deflection shape was a concave(Type I), the out-of-plane deformation became the same shape as that of the initial deflection and its magnitude became small. When the initial deflection made a winding in the welding direction(Type III), the out-of-plane deformation became large in the plate width. The initial deflection shape did not influence on residual stress and plastic strain produced by welding.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.397-397
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.176-181
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• 1996

원자로 용기 헤드부위의 관통관은 재질이 Inconel-600이며, 현재 세계각국에서도 원자로 헤드 관통관의 균열이 일부 발견되어 우리나라에서도 관심이 되고 있다. 국내 원전 헤드관 통관 수량도 고리 1,2호기의 경우 40개, 고리3,4호기(영광1,2) 61개, 울진 57개로서 관통관의 균열결함이 존재할 수 있다. 만약 균열이 성장하여 파손 되었을 시 원자로 냉각재 누설등 발전소 안전에 큰영향을 미치므로 균열의 원인으로 알려진 용접부위 잔류응력 및 발전소 정상운전 상태에서의 응력을 해석하였다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.37 no.1
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• pp.47-54
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• 2013

This study investigates the crack growth behavior due to primary water stress corrosion cracking (PWSCC) in the dissimilar metal butt weld of a reactor piping using Alloy 82/182. First, detailed finite element stress analyses were performed to predict the stress distribution of the dissimilar metal butt weld in which the hydrostatic and the normal operating loads as well as the weld residual stresses were considered to evaluate the stress redistribution due to mechanical loadings. Based on the stress distributions along the wall thickness of the dissimilar metal butt weld, the crack growth behavior of the postulated axial and circumferential cracks were predicted, from which the crack growth diagram due to PWSCC was proposed. The present results can be applied to predict the crack growth rate in the dissimilar metal butt weld of reactor piping due to PWSCC.

• Journal of the KSME
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• v.28 no.4
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• pp.322-327
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• 1988

용접구조물의 파괴는 단순 역학적인 차원을 넘어서 재료공학적 검토와 시공상의 각종 변수를 고려해야만 정확하게 이해할 수가 있으며 방지할 수 있다. 용접도중에 발생되는 미소파괴(균열) 는 적절한 재료의 선정과 적당한 시공법으로 해결할 수 있으며, 사용도중 발생되는 거시적 파 괴는 사용조건에 유의하고 발생된 용접결함을 제거할 수 있다면 방지할 수 있다. 결론적으로 용접구조물의 파괴는 용접도중에 결함을 발생시키지 않는 방법으로 방지하는 것이 가장 효과적 이기 때문에 시공법의 선정 및 실시는 충분한 검토와 주의가 필요하다. 용접품의 파괴현상을 해석하는 데는 현재까지 잘 연구되어진 각종 파괴역학적 및 피로역학적 해석이 적용될 수 있 으나 용접부의 불균일한 조직형성에 따른 기계적 성질의 불균일성과 잔류응력 등을 추가로 고 려해야 하는 것이 약간 다를 뿐이다. 현재 용접부의 취성 및 피로파괴에 대한 다방면의 연구가 활발하게 이루어지고 있는 형편이며 향후에는 용접구조물의 수명예측을 포함한 가족 파괴해석 기술이 확립될 것으로 생각된다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.1
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• pp.9-16
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• 2011

Primary water stress corrosion cracking (PWSCC) has been found in the weld region of the nuclear power plant. Welding can produce tensile residual stress. Tensile residual stress contributes to the initiation and growth of PWSCC. It is important to estimate weld residual stress accurately to predict or prevent the initiation and growth of PWSCC. This paper shows the results of finite element analysis and measurement experiment for weld residual stress. For the study, four kinds of specimen were fabricated with the materials used in the nuclear power plant. Residual stresses were measured by four kinds of methods of hole drilling, x-ray diffraction, instrumented indentation and sectioning. Through the study, numerical analysis and measurement results were compared and the characteristics of each measurement technique were observed.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.35 no.10
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• pp.1337-1345
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• 2011

In pressurized water reactors (PWRs), the reactor pressure vessel (RPV) upper head contains numerous control rod drive mechanism (CRDM) nozzles. In the last 10 years, the incidences of cracking in alloy 600 CRDM nozzles and their associated welds has increased significantly. Several axial and circumferential cracks have been found in CRDM nozzles in European PWRs and U.S. nuclear power plants. These cracks are caused by primary water stress corrosion cracking (PWSCC) and have been shown to be driven by welding residual stresses and operational stresses in the weld region. Therefore, detailed finite-element (FE) simulations for the Korea Nuclear Reactor Pressure Vessel have been conducted in order to predict the magnitudes of the weld residual stresses in the tube materials. In particular, the weld residual stress results are compared in terms for nozzle location, geometry factor$r_o$/t, geometry of fillet, and adjacent nozzle.

• Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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• 2003.05a
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• pp.274-278
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• 2003

In recent, an application of high energy density beam we/ding is increasing to obtain the high quality in weldments. Laser welding, especially, has been recognized as an useful method and its beam power has also increased according to the development of relevant technology. However, welding method in the fields of power plant is conservative because their structures have required to endure high temperature and pressure. So, authors conduct the numerical simulation in order to consider the possibility of laser welding on the material of the pressure vessels ($2\frac{1}{4}Cr-1Mo$ steel). As a result of this study, we can confirm the advantages of laser welding and obtain useful information for the experiments of weldability.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.19 no.2
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• pp.130-139
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• 2023

This paper examines the quantification of uncertainty for welding residual stresses in dissimilar metal welds used in nuclear power plants. A mock-up of a dissimilar metal weld pipe, consisting of carbon and stainless steel pipes, was fabricated to measure the residual stress. A Round-Robin analysis was conducted by Korean institutions to assess the welding residual stress. The analysis was carried out in the second order, and the data obtained by each institution was evaluated based on the information provided. Using the Round-Robin results, the distribution of uncertainty in welding residual stresses among Korean institutions was evaluated. The quantification of uncertainty for Korean institutions was found to have a wider range compared to the distribution of welding residual stresses observed in overseas institutions. This study is considered useful in the establishment of comprehensive strategies for evaluating welding residual stress analysis methods used by domestic institutions.

• Journal of the Society of Naval Architects of Korea
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• v.48 no.3
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• pp.238-245
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• 2011

Welding inevitably introduces the residual stresses which affect the fatigue strength of the joint structure. The mitigation of fatigue strength depends on the residual stress magnitude and distribution. Stress relief analyses are of practical interest for all cyclic loaded welded structures, such as ships and offshore structures. In order to estimate the effects of relaxation of residual stresses in the welded structure, this paper presents a finite element analysis procedure and experimental results for the welded structure. Cruciform specimens joint by MAG welding have been tested to measure the released stress. Relieved welding residual stresses obtained by finite element analysis are compared with those measured by experiment.