• Journal of Advanced Marine Engineering and Technology
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• 제29권4호
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• pp.399-406
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• 2005

Alloy 625 is used widely in industrial applications such as aeronautical aerospace, chemical, petrochemical and marine applications. Because of a good combination of yield strength. tensile strength, creep strength, excellent fabricability, weldability and good resistance to high temperature corrosion on prolonged exposure to aggressive environments. High qualify weldments for this material are readily produced by commonly used processes. But all of processes are not applicable to this material by reason of unavailability of matching, position or suitable welding filler metals and fluxes may limit the choice of welding processes. Recently, the flux cored wire is developed and applied for the better productivity in several welding position including the vortical position. In this study. the weldability and weldment characteristics of Alloy 625 are evaluated in FCAW weld associated with the several shielding gases($80\%Ar+20\%\;CO_2,\;50\%Ar+50\%\;CO_2.\;100\%\;CO_2$) in viewpoint of welding productivity. The results of the experimental study on corrosive characteristics of Alloy 625 are as follows; There is no remarkable difference among shielding gases. however they has a striking difference among corrosive solutions by results of distinguished density and time of corrosive solution. Generally, the shielding gases($80\%Ar+20\%\;CO_2$) was superior to the other gases on high temperature tensile and a low temperature impact. but all of the shield gases were making satisfactory results on corrosion test.

• 한국분말재료학회지
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• 제31권3호
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• pp.255-262
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• 2024

Nano-oxide dispersion-strengthened (ODS) superalloys have attracted attention because of their outstanding mechanical reinforcement mechanism. Dispersed oxides increase the material's strength by preventing grain growth and recrystallization, as well as increasing creep resistance. In this research, atomic layer deposition (ALD) was applied to synthesize an ODS alloy. It is useful to coat conformal thin films even on complex matrix shapes, such as nanorods or powders. We coated an Nb-Si-based superalloy with TiO₂ thin film by using rotary-reactor type thermal ALD. TiO₂ was grown by controlling the deposition recipe, reactor temperature, N₂ flow rate, and rotor speed. We could confirm the formation of uniform TiO₂ film on the surface of the superalloy. This process was successfully applied to the synthesis of an ODS alloy, which could be a new field of ALD applications.

• 열처리공학회지
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• 제5권1호
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• pp.41-49
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• 1992

The effects of alloying elements on the superplastic properties of Al-Li based alloys had been investigated. The intermediate thermo-mechanical treated (ITMT) Al-2.0wt%Li, Al-2.0wt%Li-1.0wt%Mg, Al-2.0wt%Li-0.12wt%Zr and Al-2.0wt%Li-1.2wt%Cu-1.0wt%Mg-0.12wt%Zr alloys were tested in tension at various temperature (400, 450, 500 and $550^{\circ}C$) and strain rate($6.7{\times}10^{-3}$, $1.0{\times}10^{-2}$, $1.6{\times}10^{-2}$ and $5.0{\times}10^{-2}/sec$). The results were as follows : The superplasticity in binary, ternary and pentanary alloys appeared at 500 to $550^{\circ}C$, and good strain rate for superplasticity. $1.6{\times}10^{-2}/sec{\sim}1.0{\times}10^{-2}/sec$ for a binary alloy and $1.0{\times}10^{-2}/sec{\sim}6.7{\times}10^{-3}/sec$ for ternary and pentanary alloys. A Zr-added ternary alloy had best value of elongation (730%) in four alloys at $550^{\circ}C$ of tension temperature and $1.0{\times}10^{-2}/sec$ of strain rate. The strain rate was greatly dependent on tension temperature and true strain rate was more than 1.0 at all test temperature and strain rate. In binary and Mg-added teranry alloys. the necks were slightly formed and their fracture surface had lips shape, but Zr-added ternary and pentanary alloy fractured along the grain boundary without necking. Their dislocations moved to grain boundary during superplasticity deformation and arranged perpendicular to grain boundary. Super plastic deformation was made by grain boundary slip of dislocation slip creep and model of core and mantle.

• 한국농공학회지
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• 제39권3호
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• pp.72-82
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• 1997

In all inelastic deformations time rate effects are always present to some degree. Whether or not their exclusion has a significant influence on the prediction of the material behaviour depends upon several factors. In the study of structural components under static loading conditions at normal temperature it is accepted that time rate effects are generally not important. However metals, especially under high temperatures, exhibit simultaneously the phenomena of creep and viscoplasticity. In this study, elastoplastic and elasto-viscoplastic models include nonlinear geometrical effects were developed and several numerical examples are also included to verify the computer programming work developed here in this work. Comparisons of the calculated results, for the elasto-viscoplastic analysis of an internally pressurised thick cylinder under plane strain condition, have shown that the model yields excellent results. The results obtained from the numerical examples for an elasto-viscoplastic analysis of the Nuclear Reinforced Concrete Containment Structure(NRCCS) subjected to an incrementally applied internal pressure were summarized as follows : 1. The steady state hoop stress distribution along the shell layer of dome and dome wall junction part of NRCCS were linearly behave and the stress in interior surfaces was larger than that in exterior. 2.However in the upper part of the wall of NRCCS the steady state hoop stress in creased linearly from its inner to outer surfaces, being the exact reverse to the previous case of dome/dome-wall junction part. 3.At the lower part of wall of NRCCS, the linear change of steady state hoop stress along its wall layer began to disturb above a certain level of load increase.

• 콘크리트학회논문집
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• 제13권6호
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• pp.568-574
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• 2001

콘크리트 시험편에 대한 삼점휨실험을 실시하여 여러 실험에 대해 측정된 반응의 평균값을 계산하곤 계산된 평균거동으로부터 삼점휨 시험편이 완전히 파손될 때까지 연속적으로 성장하는 균열에 대한 파괴거동이 분석되었다. 이 연구에서 사용된 실험변수는 25.4mm와 6.4mm의 초기균열길이 그리고 2000sec와 20sec의 실험기간이며, 초기균열길이는 파괴진행대(FPZ) 크기의 영향과 시험편의 기하학적 특성 및 경계조건에 대한 영향을 분석하기 위한 것이다. 실험기간은 초기 크리프(creep)의 영향을 위해 설정되었으나, 이 연구의 하중점-변위 속도에서는 심각한 영향이 관측되지 않았다. 여러 실험의 평균 외부일로부터 평균하중이 계산되었으며, 변형률 게이지를 사용하여 평균 균열길이를 측정하였다. 최대하중 이전의 저항곡선은 파괴진행대의 크기에 대해 유사한 값을 보였다. 그러나 최대하중 직후에는 초기균열의 크기에 관계없이 0.088~0.154mm의 하중점-변위에서 88mm의 불안정 균열성장이 발생되었으며, 평균 파괴에너지율 $G_{F}$$^{ave}$ = 115N/m은 이 불안정 균열성장 동안에 발생되었다. 균열길이 111mm에서 완전한 파괴진행대가 형성되었고, 25.4mm와 6.4mm의 초기균열길이에 대해 파괴진행대의 크기는 각각 86mm와 105mm이었다. 완전한 파괴진행대의 형성이후 저항곡선의 평균 파괴에너지율은 25.4mm와 6.4mm의 초기균열길이에 대해 각각 229N/m로 284N/m로 $G_{F}$$^{ave}$의 두 배 이상이었다.이었다.이었다.

• 콘크리트학회논문집
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• 제25권6호
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• pp.613-620
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• 2013

콘크리트는 고온에 강한재료로 인식되어 왔으나, 화재 등의 고온에 의해 내부조직의 물리 화학적 변화가 발생해 역학적 특성이 저하하게 된다. 이에, 고온시 콘크리트의 역학적 특성의 저하에 관한 연구보고 및 기준이 제시되고 있다. 그러나 고강도 콘크리트 및 하중을 재하한 상태에 관한 연구데이터는 적다. 따라서 이 연구에서는 고온 및 하중재하에 따른 고강도 콘크리트의 고온특성을 평가하였다. W/B 12.5%, 14.5%, 20%의 고강도 콘크리트를 대상으로 비재하상태 및 $0.25f_{cu}$의 하중조건을 설정하여, 고온시의 응력-변형, 최대하중에서의 변형, 압축강도, 탄성계수, 열팽창변형, 단기 고온크리프을 평가하였다. 실험 결과, 압축강도가 높아질수록 가열에 의한 압축강도의 저하가 크게 나타났고, $500^{\circ}C$이상의 온도에서 고온에 의한 열팽창변형과 하중재하에 의한 수축변형이 상쇄되어 압축강도 및 탄성계수의 잔존율이 높아지는 것을 확인할 수 있었다.

• 콘크리트학회논문집
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• 제15권2호
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• pp.280-287
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• 2003

산업폐기물 중 하나인 굴패각(Oyster Shell, OS)에 대한 건설재료로써의 활용성을 검토하기 위해 굴패각을 혼합한 콘크리트의 장기역학적 특성과 내구성을 실험적으로 평가하였다. 실험결과에 따르면 굴패각을 10% 대체한 콘크리트의 장기강도는 굴패각을 대체하지 않은 콘크리트와 유사한 결과를 보였으나, 굴패각을 20% 대체한 콘크리트의 장기강도는 감소하는 것을 보였다. 즉, 일정 한도 이상의 굴패각 대체는 콘크리트의 장기재령 강도에 열화요인으로 작용할 수 있는 것으로 나타났고, 굴패각의 대체에 따른 탄성계수 저하는 대체율에 거의 비례적으로 저하하였으며 굴패각의 대체율 20%에서 약 10∼15% 저하하였다. 굴패각의 대체율이 증가할수록 건조수축 발생량은 증가하였으며 기존의 건조수축과 크리프 모델식은 굴패각의 증가에 따른 영향을 잘 반영하지 못하였고 이에 대한 예측식의 보정이 필요하다. 잔골재의 일부를 굴패각으로 대체하여도 콘크리트의 동결융해 저항성, 탄산화 저항성, 및 화학침식 저항성에는 나쁜 영향을 미치지 않으며, 투수 저항성은 오히려 크게 개선되었다.

• Corrosion Science and Technology
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• 제12권2호
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• pp.102-112
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• 2013

A very high-temperature gas reactor (VHTR) is one of the next generation nuclear reactors owing to its safety, high energy efficiency, and proliferation-resistance. Heat is transferred from the primary helium loop to the secondary helium loop through an intermediate heat exchanger (IHX). Under VHTR environment Alloy 617 is being considered a candidate Ni-based superalloy for the IHX of a VHTR, owing to its good creep resistance, phase stability and corrosion resistance at high temperature. In this study, high-temperature corrosion tests were carried out at 850 - $950^{\circ}C$ in air and impure helium environments. Alloy 617 specimens showed a parabolic oxidation behavior for all temperatures and environments. The activation energy for oxidation was 154 kJ/mol in helium environment, and 261 kJ/mol in an air environment. The scanning electron microscope (SEM) and energy-dispersive x-ray spectroscopy (EDS) results revealed that there were a Cr-rich surface oxide layer, Al-rich internal oxides and depletion of grain boundary carbide after corrosion test. The thickness and depths of degraded layers also showed a parabolic relationship with the time. A corrosion rate of $950^{\circ}C$ in impure helium was higher than that in an air environment, caused by difference in the outer oxide morphology.

• 한국지반공학회논문집
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• 제21권3호
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• pp.133-140
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• 2005

연약지반에서 압밀속도를 가속화시키고 설계 전단강도를 얻기 위하여 선행압밀공법과 병행된 연직배수공법이 널리 사용되어 왔다. 본 연구에서는 배수계가 설치된 연약지반에서 압밀과정 동안에 간극비의 감소로 인한 압축성과 투수계수의 변화를 고려할 뿐만 아니라 1차압밀 동안에 유발되는 2차압밀(혹은 크리프)을 고려할 수 있는 축대칭 비선형 압밀이론이 개발되었다. 측대칭 비선형 압밀해석을 위한 수치해석 프로그램, AXICON은 가정 B를 바탕으로 유한차분법을 적용하여 개발되었다. 가정 A를 바탕으로 한 Hansbo의 해석적인 해와 AXICON 해석결과를 비교$\cdot$분석하였다. 또한 Ska-Edeby 시험성토 현장지반에서 관측된 침하량과 간극수압의 계측자료와 비교하였다. 해석결과에 의하면 가정 A는 현장침하량을 일반적으로 과소 평가하며, 가정 B가 논리적으로 타당하다. 또한 제안된 해석 프로그램을 사용하면 실제 현장의 거동을 잘 예측할 수 있다.

• Nuclear Engineering and Technology
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• 제52권3호
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• pp.597-609
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• 2020

Accident Tolerant Fuels have been widely studied since the Fukushima-Daiichi accident in 2011 as one of the options on how to further enhance the safety of nuclear power plants. Deposition of protective coatings on nuclear fuel claddings has been considered as a near-term concept that will reduce the high-temperature oxidation rate and enhance accidental tolerance of the cladding while providing additional benefits during normal operation and transients. This study focuses on experimental testing of Zr-based alloys coated with Cr-based coatings using Physical Vapour Deposition. The results of long-term corrosion tests, as well as tests simulating postulated accidents, are presented. Zr-1%Nb alloy used as nuclear fuel cladding serves as a substrate and Cr, CrN, Cr_xN_y layers are deposited by unbalanced magnetron sputtering and reactive magnetron sputtering. The deposition procedures are optimized in order to improve coating properties. Coated as well as reference uncoated samples were experimentally tested. The presented results include standard long-term corrosion tests at 360℃ in WWER water chemistry, burst (creep) tests and mainly single and double-sided high-temperature steam oxidation tests between 1000 and 1400℃ related to postulated Loss-of-coolant accident and Design extension conditions. Coated and reference samples were characterized pre- and post-testing using mechanical testing (microhardness, ring compression test), Thermal Evolved Gas Analysis analysis (hydrogen, oxygen concentration), optical microscopy, scanning electron microscopy (EDS, WDS, EBSD) and X-ray diffraction.