• Journal of Welding and Joining
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• 제6권2호
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• pp.30-39
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• 1988

Generally, as the welded region of weld structures has the incomplete bead and welded deposit which are able to behave like the surface cracks occasinally, there is a high possibility that the fatigue fracture of the weld structures is due to the surface cracks on the wlded region. This study was done to investigate the effects of post weld heat treatment (PWHT) on the fatigue behaviors of the surface crack of the heat affected zone (HAZ) for the multi-pass welds under the repetitive pure bending moment. The obtained results are summarized as follows : 1. The crack grows to the depth direction initially as the number of cylces increase, the amount of crack length is increased for the surface dir3ction and cive versa for the depth direction. 2. The fatigue life is increased in a order of as weld, PWHT specimens and parent. 3. As the number of cycles increase, the crack length is increased to th surface direction. The increase of the depth length is blunted at the center of specimen thickness. 4. The fatigue crack growth of PWHT specimens to the surface direction is dependent upon the holding time and applied stress during PWHT. In order words, the crack growth rate decreases with the holding time and increases with the applied stress during PWHT. 5. As the crack grows, the aspect formed in the course of crack propagation approaches to semicircle for parent and ellipse with the largest semidiameter for PWHT ($1/4hr, 15kgf/mm^2$) 6. At depth direction, it is difficult to apply to the paris' equation because of the scattered data between the crack growth rate and the stress intensity factor range.

• 비파괴검사학회지
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• 제21권1호
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• pp.62-68
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• 2001

인공해수에서 HT-60강 용접부의 응력부식균열(SCC)과 음향방출(AE)신호특성을 알아보기 위하여 SCC외 AE실험을 동시에 실시하였으며, 양 실험결과를 상호 비교 분석하였다. 모재의 경우, -0.8V에서 보다 긴 파단수명을 보였고, 용해기구 등으로 인하여 -0.8V에 비해 -0.5V에서 AE가 많이 발생하였다. 그러나 시험편에 가해진 전위 값에 관계없이 최대하중 이후의 영역에서 AE 발생 수는 감소하였다. 용접재의 경우, 모재 및 후열처리재와는 달리 용접부의 특이성 때문에 많은 AE 발생과 큰 진폭의 범위$(40{\sim}100dB)$를 나타내었으며 최대하중 이후에도 AE 발생이 활발하였다. 또한, 보다 크고 많은 균열이 파단면에 형성되었음을 SEM관찰을 통하여 관찰할 수 있었으며, 이들 결과로부터 용접부는 인공해수에서 SCC현상이 가장 심하게 일어나고 있음을 확인할 수 있었다. 후열처리는 용접부의 연화를 초래하였고, 용접재에 비해 부식환경에 대한 민감도를 떨어뜨리는 효과를 가져왔다.

• Journal of Welding and Joining
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• 제10권3호
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• pp.40-53
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• 1992

고온고압장치(High Temperature and Pressure Vessels)의 적용을 위한 기초연구로서 9Cr-1Mo강 용접부의 연화특성에 대하여 검토하였다. 9Cr-1Mo 강재에 Bead-on-Plate용접을 실시한 후, 용접부의 기계적 성질과 그 현미경조직관찰 및 미세경도를 측정한 결과, As-Welded 및 용접 후열처리(PWHT)등의 조건에 관계없이 용접열향부의 변태역과 템퍼링역의 경계에서 모재의 경 도보다 낮은 경도값(연화역)을 나타내었으며 이러한 원인은 결정립계(Grain boundary)에 석출 되는 탄화물의 형성에 의한 뜨임 현상임이 판명되었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 추계학술발표회논문집(2)
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• pp.557-562
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• 1996

조사전 및 감시시험시 용접열영향부(heat affected zone, HAZ)의 인성평가를 위해 제작되는 샤피(Charpy) 충격시험편의 노치(notch) 위치에 대하여 현재의 규정에 대한 타당성을 검토하였다. 적용규정은 HAZ 시험편의 노치위치를 용접용융선(fusion line, FL) ＋ 모재측 0.8 mm 로 제한하고 있다. 그러나, 본 연구결과, 이 부위는 다층(multipass) 용접시 후속열이력에 의해 결정립이 미세화되어, 인장강도와 경도 및 충격인성이 모재나 용접부에 비하여 양호하게 나타났다. 한편, FL ＋ 4 mm 이상의 다른 위치에서는 강도와 경도 및 충격인성이 모두 모재와 용접부에 비하여 낮은 값을 보였다. 이는 다층용접에 의한 후속열이력 및 용접후열처리(post weld heat treatment, PWHT)에 의해 금속조직학적 영향을 받은 것으로 판단되었다. 일련의 시험결과로부터, 조 사전 및 감시시험용 샤피충격시험편의 HAZ 에 있어서의 노치위치에 대한 현재의 규정을 재검토할 필요가 있음을 제안하였다.

• 대한기계학회논문집
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• 제9권1호
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• pp.40-46
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• 1985

본 연구에서는 제 1보에 밝힌 바 있는 용접 HAZ조직의 파괴인성에 영향을 주 는 PWHT 유지시간과 가열속도에 이어, 용접 HAZ의 불안정포성파괴에 미치는 용접잔유 응력의 영향을 상세히 밝히기 위하여 일층 용접을 실시하고, 이 용접재의 용접HAZ에 단축상태의 일정한 응력을 작용시켜 주면서 소정의 열처리를 실시함으로써 용접후 열 처리시 용접HAZ에 작용된 응력의 크기가 파괴인성에 어떠한 영향을 미치는지를 COD파 괴인성시험, 미소경도시험, 파면관찰을 통하여 고찰하고자 한다.

• 한국정밀공학회지
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• 제33권7호
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• pp.551-558
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• 2016

Reduction of welding residual stress is very important in the railway industry, but calculating its distribution in structures is difficult because welding residual stress formation is influenced by various parameters. In this study, we developed a finite element model for simulating the repair welding process to recover a surface damaged rail, and conducted a series of parametric studies while varying the cooling rate and the duration of post weld heat treatment (PWHT) to find the best conditions for reducing welding residual stress level. This paper presents a three-dimensional model of the repair welding process considering the phase transformation effect implemented by the ABAQUS user subroutine, and the results of parametric studies with various cooling rates and PWHT durations. We found that heat treatment significantly reduced the residual stress on the upper rail by about 170 MPa.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1862-1870
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• 2020

The purpose of this study is to investigate the effect of welding residual stress on operating stress in designing a nuclear turbine welded rotor. A two-dimensional axisymmetric finite element model is employed to calculate the residual stress before and after post weld heat treatment (PWHT), and then the superposition of residual stress after PWHT and operating stress at normal speed and overspeed were discussed. The investigated results show that operating stress can be affected significantly by welding residual stress, and the distribution trend of superposition stress at the weld area is mainly determined by welding residual stress. The superposition of residual stress and operating stress is linear superposition, and the hoop stress distribution of superposition stress is similar with the distribution of residual stress. With the increasing overspeed, the distribution pattern of the hoop superimposed stress remains almost unchanged, while the stress level increases.

• 대한기계학회논문집A
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• 제24권10호
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• pp.2597-2602
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• 2000

The most effective means of evaluating remaining life is through the creep testing of samples removed from the component. But sampling of large specimen from in-service component is actually impossible. So, sampling device and small-specimen creep tester have been applied. Sampling device has been devised to extract mechanically small samples by hemispherical, diamond -coated cutter from the surface of turbine rotor bores and thick-walled pipes without subsequent weld repairs requiring post weld heat treatment. A method of manufacturing small creep specimen, 2min gage diameter and 10min gage length, using electron beam welding to attach grip section, has been proven. Small-specimen creep tester has been designed to control atmosphere to prevent stress increment by oxidation during experiment. To determine whether the small specimens successfully reproduce the behavior of large specimens, creep rupture tests for small and large specimens have been performed at identical conditions. Creep rupture times based on small specimens have closely agreed within 5% error compared with that of large specimen. The errors in rupture time have decreased at longer test period. This comparison validates the procedure for fabricating and testing on small specimen. This technique offers potential as an efficient method for remaining life assessment by direct sampling from in -service high temperature components.

• Journal of Welding and Joining
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• 제5권3호
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• pp.53-61
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• 1987

Post weld heat treatment(PWHT) is usually carried out to remove the residual stress and to improve the microstructure and mechanical properties of welded joints. By the way, welding structure transformed owing to PWHT and reheating for repair loads the random cycles fatigue as offshore welding structure of constant low cycle fatigue as pressure vessel, and then, pre-existing flaws or cracks exist in a structural component and those cracks grow under cyclic loading. Therefore, the effects of PWHT and stress ratio on fatigue crack growth behaviors were studied on the three regions such as HAZ, sub-critical HAZ and deposit metal of welded joints in SM53 steel. Fatigue crack growth behavior of as-weld depended on microstructure and fatigue crack growth rate of HAZ was the lowest at eac region, but after PWHT it was somewhat higher than that of as-wel. In case of applying the stress($10kg/mm^2$) during PWHT, fatigue crack growth resistance tended to increase in the overall range of .DELTA.K.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1049-1078
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• 2021

The review summarizes the published data on the widely applied electron-beam, laser-beam, as well as resistance upset, projection, and spot welding of zirconium alloys for nuclear applications. It provides the results of their analysis to identify common patterns in this area. Great attention has been paid to the quality requirements, the edge preparation, up-to-date equipment, process parameters, as well as post-weld treatment and processing. Also, quality control and weld repair methods have been mentioned. Finally, conclusions have been drawn about a significant gap between the capabilities of advanced welding equipment to control the microstructure and, accordingly, the properties of welded joints of the zirconium alloys and existing algorithms that enable to realize them in the nuclear industry. Considering the ever-increasing demands on the high-burnup accident tolerant nuclear fuel assemblies, great efforts should be focused on the improving the welding procedures by implementing predefined heat input cycles. However, a lot of research is required, since the number of possible combinations of the zirconium alloys, designs and dimensions of the joints dramatically exceeds the quantity of published results on the effect of the welding parameters on the properties of the welds.