• 한국수소및신에너지학회논문집
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• 제35권2호
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• pp.216-229
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• 2024

Pipeline steels for hydrogen transmission may cause hydrogen embrittlement due to absorption and diffusion of hydrogen through metals. Hydrogen pipes exhibited similar mechanical properties to atmospheric conditions in terms of tensile and yield strength in a hydrogen atmosphere. This paper aims to provide relevant information regarding hydrogen embrittlement in hydrogen transmission pipeline.

• 한국가스학회지
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• 제9권4호
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• pp.30-35
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• 2005

스테인리스 강재 STS444에 있어서 용접조건에 따른 수소취성의 전기화학적 분극특성을 고찰하고자 수소침투 실험과 전기화학적 분극실험을 실시하였다. 즉, $0.5M\; H_2SO_4+0.001M\;As_2O_3$ 수용액 중에서 $1,400kg/cm^2$의 하중을 부가하는 동시에 전기화학적 분극시험 장치로 $30mA/cm^2$전류를 60분간 인가하여 수소를 침투시켰으며 같은 수용액에서 양극분극실험을 하였다. STS444에 있어서 용접조건이 수소취성에 미치는 특성을 연구함에 있어 전보에서는 용접 전 기름이나 물의 흡착 영향으로 인장강도나 연신율이 낮아지는 현상을 규명하였지만, 본보에서는 기존의 보고된 수소취성의 발생 기구를 기초로 하여 전기화학적 부식거동을 접목하여 수소취성의 발생기구를 제안함으로써 부식전류밀도를 알면 수소취성의 민감 정도를 비파괴적으로 예측할 수 있을 것으로 판단된다.

• 한국가스학회지
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• 제9권4호
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• pp.11-16
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• 2005

스테인리스 강재인 STS444에 있어서 용접조건에 따른 수소취성 거동을 고찰하고자 수소침투실험과 기계적 인장시험을 실시하였다. 즉, $0.5MH_2SO_4+0.001M \;As_2O_3$ 수용액 중에서 $1,400 kg/cm^2$의 하중을 부가하는 동시에 전기화학 부식시험 장치로 $30mA/cm^2$전류를 60분간 인가하여 수소를 침투시킨 후 기계적 인장시험을 통해서 STS444용접부의 수소취성 특성에 관해서 고찰하였다. STS444에 있어서 용접조건이 수소취성에 미치는 특성을 연구한 결과, 용접 전 기름이나 물의 흡착에 의해 인장강도나 연신율은 낮아진다. 또한 기름이나 물이 흡착함으로써 수소취성에 의한 인장응력 및 연신율의 감소율은 더 크게 나타나고, 용접 전 물의 흡착이 기름의 흡착보다 수소취성에 민감하다.

• 비파괴검사학회지
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• 제19권6호
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• pp.411-419
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• 1999

에너지 변환설비와 관련된 기계구조물의 내열재료는 $350^{\circ}C{\sim}550^{\circ}C$의 온도범위에서 장시간 사용되는데 이때 조직의 결정입계에는 불순물 원소(P, Sn, Sb등)의 편석과 탄화물의 석출 등으로 인하여 재료의 취화 현상이 발생되고, 그로 인해 입계강도의 저하가 초래된다. 따라서 노후화된 고온설비의 안전성 및 효율적인 운전조건을 확보하고, 취성파괴 방지를 위해서는 취화손상의 정량적 평가는 매우 중요하다. 그러나 가동중인 고온설비에서 파괴시험을 위한 대량의 시험편채취가 거의 불가능한 경우가 대부분이므로 비파괴적인 시험방법이 요구된다. 본 연구에서는 인공시효열처리된 2.25Cr-1Mo강의 비파괴적인 취화손상도 평가를 위해 적정 부식환경하에서 전기화학적 분극시험 방법에 의한 최적의 평가인자를 조사하였다. 또한 전기화학 시험결과들은 준비파괴시험인 SP시험에 의한 취화도 평가결과와 비교되었다.

• Journal of Welding and Joining
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• 제27권5호
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• pp.55-61
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• 2009

Pure titanium and its alloys have good formability, excellent corrosion resistance and high strength to weight ratios. Therefore, it has been using to heat exchangers, offshore plants, sports equipments, and etc. As broad as its application fields, it also increases welding locations. Conventional GTAW and GMAW are very popular welding methods of titanium, but it has a high heat input and wide HAZ. It has a possibility of inducing Stress Corrosion Cracking. So, laser welding method has been using to get reliable welds by reducing heat input. Weld beads change its color to silver, gold, brown, blue, and gray by shied conditions. And the closer to gray, the more oxidize, nitride and embrittlement. The most effective atom to embrittlement was nitrogen. And shield gas flow was not so effective over the constant flow rates. In this study, weld properties of the pure titanium were investigated by pulsed & CW Nd:YAG lasers and evaluated by various shield conditions. And It is observed that nitrogen is more effective to oxidation and embrittlement of titanium compared with oxygen by oxygen and nitrogen quantitative analysis.

• 한국기계가공학회지
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• 제15권3호
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• pp.72-78
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• 2016

In this study, we analyzed the accidental hydrogen embrittlement affecting the track nut on a self-propelled howitzer. Tracks are key components to maintain a high degree of confidence in the operation of the self-propelled howitzer and the safety of the crew. This study analyzed the fractured surface using SEM to review accidental damage of the wedge nut. In addition, we conducted revival tests and analyzed the results to identify the cause of the wedge nut damage from hydrogen embrittlement. We should carry out factor analysis and continuous improvement of the manufacturing process to determine the accidental breakage mechanism for future enhancement of the self-propelled howitzer. This study will be the useful reference for enhancing process designs in similar products.

• 열처리공학회지
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• 제12권4호
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• pp.327-337
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• 1999

A series of Ni-Cr-Mo alloy steels were austenitized, quenched to martensite, and tempered at various temperature and time conditions. Tensile testing was conducted at room temperature with cylindrical specimens, and hardness was measured using Rockwell hardness tester. In the tempering stage I, high strain hardening and yield strength accounted for the high ultimate strength and hardness. In the tempering stage II, strengths and hardness linearly decreased with increasing tempering temperature. Specimens tempered in the temperin stage III showed incipient discontinuous yielding and tensile strengths only slightly higher than yield strengths. Ductilities decreased slightly in specimens tempered in the tempered martensite embrittlement range, and severely decreased in specimens tempered for 10 hours at $500^{\circ}C$ in the temper embrittlement range. Specimens tempered at $600^{\circ}C$ for 10 hours showed recrystallized microstructures, a number of fine dimples, and increased strain hardening, probably due to the precipitation of alloy carbides. The simple formulae for the mechanical properties of these steels were suggested as a function of carbon content and Hollomon-Jaffe tempering parameter.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(3)
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• pp.79-84
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• 1996

Small punch test was performed on CF8 duplex stainless steel aged at 370 and 400$^{\circ}C$ up to 5,000 h to evaluate the degree of the thermal aging embrittlement. At room temperature, the SP load-displacement curve was in a similar shape to those of ferritic steels and had a good reproducibility in spite of two-phase structure. The aging heat treatment resulted in a slight increase of the yield strength. As test temperature was lowered, the SP load showed a sudden drop followed by serrations before the SP specimen was fractured, resulting from the cracking of ferrite phase. The extent of thermal embrittlement was assessed in terms of the SP energy. Aging treatment at higher temperature led to a larger shift in the transition temperature and the corresponding change in the fracture mode. The main cause of the degradation was the embrittlement of ferrite phase. Additionally the phase boundary separation profoundly contributed to the degradation of the specimen aged at 400$^{\circ}C$.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.11-20
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• 2009

Radiation effects on materials are inherently multiscale phenomena in view of the fact that various processes spanning a broad range of time and length scales are involved. A multiscale modeling approach to embrittlement of pressure vessel steels is presented here. The approach includes an investigation of the mechanisms of defect accumulation, microstructure evolution and the corresponding effects on mechanical properties. An understanding of these phenomena is required to predict the behavior of structural materials under irradiation. We used molecular dynamics (MD) simulations at an atomic scale to study the evolution of high-energy displacement cascade reactions. The MD simulations yield quantitative information on primary damage. Using a database of displacement cascades generated by the MD simulations, we can estimate the accumulation of defects over diffusional length and time scales by applying kinetic Monte Carlo simulations. The evolution of the local microstructure under irradiation is responsible for changes in the physical and mechanical properties of materials. Mechanical property changes in irradiated materials are modeled by dislocation dynamics simulations, which simulate a collective motion of dislocations that interact with the defects. In this paper, we present a multi scale modeling methodology that describes reactor pressure vessel embrittlement in a light water reactor environment.

• 한국수소및신에너지학회논문집
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• 제18권2호
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• pp.182-188
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• 2007

[ $Zr_{50}-Ni_{27}-Nb_{18}-Co_5$ ] amorphous alloys ribbon was prepared by a single-roller melt-spinning technique. In order to improve the hydrogen kinetics Pd-coating were carried out on each side of the amorphous ribbon. Pd prevents oxidation of Zr and catalyses the dissociation of molecular hydrogen to atomic hydrogen. In this work, the hydrogen embrittlement and surface properties on Zr-based amorphous alloys were investigated. The Zr-based amorphous alloys were characterized by X-ray diffractometry(XRD) and differential scanning calorimetry(DSC). The morphology of surface and roughness was observed by using scanning electron microscopy(SEM) and atomic force microscopy (AFM). A lattice parameter of both Pd and Zr-based amorphous alloy was increased after hydrogen permeation at 473 K. After hydrogen permeation at 473 K, some cracks were observed on the surface of Pd, which was the cause for the hydrogen embrittlement. The crystallization temperature of Zr-based amorphous alloy was decreased due to the permeated hydrogen.