• Tribology and Lubricants
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• 제17권5호
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• pp.380-385
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• 2001

In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in fretting wear damage due to contacts between the tubes and their supports. In this paper the fretting wear tests and the sliding wear tests were performed using the steam generator tube materials of Inconel 600 and 690 against STS 304. Sliding tests with the pin-on-disk type tribometer were done under various applied loads and sliding speeds at air environment. Fretting tests were done under various vibrating amplitudes and applied normal loads. From the results of sliding and fretting wear tests, the wear of Inconel 600 and 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and often drastically different wear rates can occur. It was found the results that the wear coefficients for Inconel 600 and 690 were 262.3$\times$10$\^$-15/Pa$\^$-1/ and 209.2$\times$10$\^$-15/Pa$\^$-1/, respectively. This study shows that Inconel 690 can provide much better wear resistance than Inconel 600 in air.

• 대한기계학회논문집A
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• 제27권3호
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• pp.432-439
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• 2003

Inconel 690 for nuclear steam generator tube has more Chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. To evaluate the tribological characteristics of Inconel 690 under fretting condition the fretting tests were carried out in air and elevated temperature water. Fretting tests of the cross-cylinder type were done under various vibrating amplitudes and applied normal loads in order to measure the friction forces and wear volumes. From the results of fretting wear tests. the wear of Inconel 690 can be predictable using the work rate model. The amounts of friction forces were proportional to relative movement between two fretting surfaces. The friction coefficients were decreased as increasing the normal loads and deceasing the vibrating amplitudes. Depending on fretting environment, distinctively different wear mechanisms and often drastically different wear rates can occur It was found that the fretting wearfactors in air and water at 2$0^{\circ}C$, 5$0^{\circ}C$, and 8$0^{\circ}C$ were 7.38 $\times$ $10^{-13}$$Pa^{-1}$, 2.12 $\times$$10^{-13}$$Pa^{-1}$, 3.34$\times$$10^{-13}$$Pa^{-1}$and 5.21$\times$$10^{-13}$$Pa^{-1}$, respectively flexibility to model response data with multiple local extreme. In this study, metamodeling techniques are adopted to carry out the shape optimization of a funnel of Cathode Ray Tube, which finds the shape minimizing the local maximum principal stress. Optimum designs using two metamodels are compared and proper metamodel is recommended based on this research.

• KSTLE International Journal
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• 제3권1호
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• pp.49-53
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• 2002

Inconel 690 for nuclear steam generator tube has more chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. TD evaluate the tribological characteristics under fretting condition the fretting tests as well as sliding tests were carried out in elevated temperature water environment. Fretting tests of the cross-cylinder type were done under various vibrating amplitudes and applied normal loads in order to measure the friction forces and wear volumes. Also, the conventional sliding tests of pin-en-disk type were carried out to compare the test results. In fretting, the friction was very sensitive to the load and the amplitude. The friction coefficient decreased with increasing load and decreasing amplitude. Also, the wear of Inconel 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and of ten drastically different wear rates can occur. It was fecund that the fretting wear coefficients in water were increased as increasing the temperature of water.

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2001년도 제33회 춘계학술대회 개최
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• pp.115-121
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• 2001

The wear test has been performed to evaluate the wear mechanism of steam generator (SG) tube materials against ferritic stainless steel in water environment. The wear rates of SG tube materials depend on the change of mechanical properties between contact surfaces during wear test. From the subsurface hardness test, Inconel 690 is more work-hardened than Inconel 600 even though these materials have similar hardness values before the wear test. Main cause is due to the difference of stacking fault energy with the chromium content. In water environment, wear mechanism is closely related with the continuous formation and fracture of deformation layers at the contact surfaces.

• Nuclear Engineering and Technology
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• 제34권2호
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• pp.132-141
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• 2002

The effects of microstructure on fretting wear were investigated in Inconel 690 tube. The microstructure observation indicated that the solution annealing temperature and time affected the grain size of the Inconel 690 tubes. The carbide morphology, along grain boundaries, was mainly affected by thermal treatment time and temperature. The wear test results showed that specimens with larger grain size and with coarse carbides along grain boundaries had better wear resistance. Cracks were found in specimens with carbides along the grain boundary, while few cracks were found in carbide free specimens. It seemed that the carbides on grain boundary assisted crack formation and propagation in carbide containing specimens. On the other hand, the micro-hardness of specimen did not have a major role in fretting wear. It could be inferred from the SEM images of worn surfaces that the main wear mechanism of carbide containing specimen was delamination, while that of carbide free specimen was abrasion.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.956-960
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• 1995

원자력발전소 증기발생기 전열관의 레이저 보수용접 기술개발을 위해 Inconel tube의 sleeve 레이저 용접실험을 수행하였다. Nd:YAG 레이저로부터 발진된 레이저 빔은 광섬유를 통하여 전송되어 자체 개발한 weld head tool을 이용하여 tube 내부에서 용접이 이뤄지도록 하였다. 레이저의 출력 및 펄스폭, 반복율, buffer 가스속도, 용접속도 등의 용접 변수를 변화시키면서 용접단면의 형상을 측정하였다. 용접변수에 따른 결과를 고찰하였고 이에 따른 적절한 용접범위를 제시하였다.

• 방사성폐기물학회지
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• 제4권2호
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• pp.103-116
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• 2006

본 논문은 국내 PWR 발전소에서 S/G tube 재질로 사용되고 있는 Inconel 600 및 690에 대한 부식 실험을 수행함으로써 작업자들의 주요 피폭원인 $^{58}Co,\;^{60}Co,\;^{51}Cr,\;^{54}Mn,\;^{59}Fe$의 생성량을 예측하고자 하였다. 이를 위해 Inconel 600 및 690 재질로 총 12개의 시편을 제작하여 실제 발전소의 운전조건과 유사하거나 가혹한 조건에서 전면 부식실험을 pH별로 20일씩 총 60일간 수행하였고, 실험 결과를 정량적으로 분석하기 위해 GDS(Glow Discharge Spectrometer) 장비를 사용하였다. GDS 장비를 이용하여 정량적으로 분석한 결과 pH 7 및 9에서는 Inconel 600이 Inconel 690에 비해 부식이 잘 되는 것으로 나타난 반면, pH 4에서는 Inconel 690이 부식이 더 잘 되는 것으로 평가되었다. 이러한 경향을 보이는 것은 과도상태의 영향이 과도하게 반영된 것에 기인한 것으로 비교적 정확한 결론을 도출하기 위해서는 장시간의 부식 실험을 수행함으로써 과도상태에 의한 영향을 최소화해야 할 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제43권5호
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• pp.469-476
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• 2011

The inner surfaces of bundled inconel tubes from steam generators in South Korean nuclear power plants are contaminated with cobalt and abrasive blasting equipment has been developed to efficiently remove the cobalt. The principal parameters related to the efficient removal using this equipment are the type of abrasive, the distance from the nozzle, and the blasting time. Preliminary tests were performed using oxidized inconel samples which enabled the simulation of cobalt removal from the radioactive inconel samples. The oxygen in the oxidized samples and the cobalt in the radioactive inconel were removed more effectively using the blasting distance, blasting time, and a silicon carbide abrasive. Using the developed abrasive blasting equipment, the optimum decontamination conditions for radioactive inconel samples were blasting for more than 6 minutes using silicon carbides under 5 atmospheric pressures.

• 해양환경안전학회지
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• 제27권1호
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• pp.187-192
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• 2021

본 연구는 절탄기 튜브의 저온부식 손상을 방지하기 위해 Inconel 625 용사재료를 활용하여 아크 열용사 코팅기술 적용 후 실링처리를 실시하였다. 용사코팅(TSC) 층의 내식성 분석을 위해 0.5 wt% 황산 수용액에서 다양한 전기화학적 실험을 진행하였다. 양극분극 실험 후에는 주사전자현미경과 EDS 성분분석을 통해 부식 손상 정도를 파악하였다. 자연전위 계측 시 TSC+실링처리(TSC+Sealing)의 안정적인 전위 형성을 통해 실링처리 효과를 확인하였다. 양극분극 실험 결과 TSC와 TSC+Sealing에서 부동태 영역이 확인되었으며, 부식 손상 역시 관찰되지 않아 내식성이 개선되었다. 더불어 타펠분석에 의해 산출된 부식전위와 부식전류밀도 분석 결과 TSC+Sealing의 내식성이 가장 우수하게 나타났다.

• 한국재료학회지
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• 제17권10호
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• pp.555-559
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• 2007

The mechanical properties and microstructure of Inconel 690 and 600 alloys with various cooling rates were investigated. Optical microscopy and scanning electron microscopy observations indicated that in case of the cooling rate of $0.5^{\circ}C/min$, discontinuous carbides along the grain boundaries were formed and when the cooling rate was $10^{\circ}C/min$, continuous carbides were formed in Inconel 690 and 600 alloys. For the annealed Inconel 690 alloy with high Cr content, a lot of annealing twins, which led the preferential growth of (111) planes, were observed. However, the annealed Inconel 600 alloy with low Cr content showed a few annealing twins and the preferential growth of (200) planes. Inconel 600 alloy had a larger value of ultimate tensile strength (UTS) than Inconel 690 alloy.