• Nuclear Engineering and Technology
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• v.51 no.2
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• pp.579-587
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• 2019

This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations.

• Journal of Welding and Joining
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• v.20 no.2
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• pp.82-89
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• 2002

In order to clarify hot cracking phenomena occurred in Inconel 690 welds and it's prevention, in this study, the cracking behavior and the influence of welding variables on cracking in Inconel 690 overlay welds on Mn-Ni-Cr-Mo steel(SA 508 cl.3) for pressure vessel were investigated by using mock-up test. The main results are as follows: The cracks in Inconel 690 overlay welds were mainly generated near the start and the end part of welding beads adjacent to STS 309L welded outside of Inconel 690 welds. Most of the cracks showed typical solidification crack, and also it was assumed that there was possibility of liquation cracking in HAZ. The existence of Nb constituents or concentration of Nb was recognized on the fracture facets of the solidification cracks in the welds by SMAW. Therefore Nb was considered to be the main factor of the solidification cracking. As the weld heat input was more increased and the weld bead length was longer, the extent of cracking was more increased. Moreover the extent of cracking was considerably decreased by changing of welding sequence to the start and the end part of welds. Hot cracking in welds by GTAW was considerably decreased as compared with that of SMAW. And cracks were well generated in the Inconel 690 overlay welds adjacent to 575 309L welds. This means that the hot cracking susceptibility of Inconel 690 welds was largely varied by chemical components and/or compositions of filter metals, base metals and neighboring welds.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.987-988
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.851-852
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• 2004

• Corrosion Science and Technology
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• v.20 no.1
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• pp.22-25
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• 2021

In the past, Alloy 600 nickel-based alloys have been widely used in steam generators. However, most of them have been replaced by thermally treated alloy 690 tubes in recent years because mill annealed alloy 600 materials are known to be susceptible to stress corrosion cracking. Unlike this general perception, some steam generators using mill annealed alloy 600 tubes show excellent performance even though they are designed, manufactured, and operated in the same way. Therefore, various analyses were carried out to determine causes for the degradation of steam generators. Based on the general stress corrosion cracking mechanism, tube material susceptibility, residual stress, and sludge deposits of steam generators were compared to identify factors affecting stress corrosion cracking. It was found that mill annealed alloy 600 steam generator tubes showed higher resistance to stress corrosion cracking when the amount of sludge deposits on tube surface was smaller and residual stress generated during the fabrication was lower.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2014.11a
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• pp.118-119
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• 2014

원전 운전 중 2차계통 구성재료가 부식되어 철 산화물이 증기발생기 내부로 유입된다. 유입된 철산화물은 고온고압의 환경에서 침적되어 슬러지가 된다. 침적된 슬러지는 증기발생기 전열관 재료에 응력부식균열(SCC)을 일으키는 주원인으로 원전에서는 철 산화물의 유입을 최소화하기 위해 기동전 2차계통을 순환 세정하고 있다. 해외 원전에서는 고분자 아크릴산(Polyacrylic Acid)을 순환세정시 주입함으로써 2차계통 철 산화물 제거 효율을 높인 사례가 있었다. 이에 우리 원전에서도 기동전 순환세정시 고분자 아크릴산을 주입 적용하였다. 고분자 아크릴산 주입 전 필수적으로 이뤄져야할 연구는 고분자 아크릴산이 재료에 미치는 영향평가이다. 본 연구에서는 고분자 아크릴산 농도(1, 10, 100 ppm)에 따라 2차계통 구성재료인 SA106 Gr.B와 Alloy 690의 건전성에 미치는 영향를 수행하였다. 평가방법으로는 전기화학 분극실험, 시편을 침지시켜 실험 전, 후 무게 감량을 이용한 부식률 측정, 표면 상태분석등을 이용하여 종합적으로 평가하였다. 전기화학 분극실험과 부식률 측정결과, 고분자 아크릴산 농도가 높을수록 부식은 증가하였고 고분자 아크릴산 농도 100 ppm일 때 최대 부식률이 0.037 mils로 계산되었다. 이는 부식허용 기준치(5.8 mils)보다는 100배이상 낮았으며 표면분석 결과 고분자 아크릴산으로 인한 pitting 부식은 발생하지 않았다. 이와 같은 결과로 기동시 환경에서 고분자 아크릴산 농도 100 ppm까지는 재료 건전성에 미치는 영향은 거의 없는 것으로 판단된다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.151-157
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• 1996

Cr 함량이 alloy 600과 alloy 690의 Cr함량 사이에 위치하는 Ni-Cr-Fe 합금을 진공유도 용해법을 이용하여 제조하였다. 합금 인고트에 대하여 열간 가공성 시험을 수행하여 열간 압연 조건을 구하였다. 열간 및 냉간 압연을 거친 시편을 900~120$0^{\circ}C$ 사이의 여러 온도에서 소둔 열처리하였고, 열처리한 시편에 대하여 기계적 특성과 부식특성을 측정, 분석하였다. Cr 함량은 기계적 강도에는 다소 영향을 미치는 것이 발견되었으나 연신율에는 거의 영향을 미치지 않는 것으로 나타났다. 부식속도는 Cr 함량 변화보다 소둔 열처리 온도에 따라 증가하였으며, 110$0^{\circ}C$ 에서 열처리한 경우에는 부식속도가 얼마간 감소하는 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.690-695
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• 1998

원자력시설에서 배출되는 고준위 방사선 페기물이나 TRU 둥의 심지층처분의 보완책으로서 핵변환 (Transmutation) 처리방안이 연구되고 있다 이 핵변환시스템의 냉각재로서 액체금속류가 고려되고 있다. 본 연구에서는 핵변환로에 적합한 냉각물질을 도출하기 위해서 보다 합리적인 선정방법으로서 의사결정방법을 이용하여 중점비교 대상인 나트륨(Na), 나트륨-칼륨 합금(Na-K alloy), 납(Pb), 납-비스므스 합금(Pb-Bi alloy)에 대한 정량적 평가를 시도하였다. 아울러 이 냉각재 후보물질에 대한 냉각재로서의 적합성 여부를 비교 검토하였다. 본 방법을 이용한 결과 핵 변화로의 냉각재로서는 납-비스므스 합금이 가장 적합한 것으로 평가되었다.

• Nuclear Engineering and Technology
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• v.44 no.5
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• pp.491-500
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• 2012

The dissimilar metal joints welded between Ni-based alloy, Alloy 690 and low alloy steel, A533 Gr. B with Alloy 152 filler metal were characterized by using optical microscope, scanning electron microscope, transmission electron microscope, secondary ion mass spectrometry and 3-dimensional atom probe tomography. It was found that in the weld root region, the weld was divided into several regions including unmixed zone in Ni-base alloy, fusion boundary, and heat-affected zone in the low alloy steel. The result of nanostructural and nanochemical analyses in this study showed the non-homogeneous distribution of elements with higher Fe but lower Mn, Ni and Cr in A533 Gr. B compared with Alloy 152, and the precipitation of carbides near the fusion boundary.

• Nuclear Engineering and Technology
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• v.44 no.6
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• pp.673-682
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• 2012

Three dimensional atom probe tomography (3D APT) is applied to characterize the dissimilar metal joint which was welded between the Ni-based alloy, Alloy 690 and the low alloy steel, A533 Gr. B, with Alloy 152 filler metal. While there is some difficulty in preparing the specimen for the analysis, the 3D APT has a truly quantitative analytical capability to characterize nanometer scale particles in metallic materials, thus its application to the microstructural analysis in multi-component metallic materials provides critical information on the mechanism of nanoscale microstructural evolution. In this study, the procedure for 3D APT specimen preparation was established, and those for dissimilar metal weld interface were prepared near the fusion boundary by a focused ion beam. The result of the analysis in this study showed the precipitation of chromium carbides near the fusion boundary between A533 Gr. B and Alloy 152.