• Title/Summary/Keyword: 취화

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Zn-Flash 코팅 처리가 전기아연도금 시 초고강도 강재의 수소 발생, 유입 및 취화 거동에 미치는 영향 (Effects of Zn-Flash Coating on Hydrogen Evolution, Infusion, and Embrittlement of Advanced-High-Strength Steel During Electro-Galvanizing)

  • 방혜린;김상헌;김성진
    • Corrosion Science and Technology
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    • 제22권5호
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    • pp.341-350
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    • 2023
  • In the present study, effects of a thin Zn-flash coating on hydrogen evolution, infusion, and embrittlement of advanced high strength steel during electro-galvanizing were examined. The electrochemical permeation technique in conjunction with impedance spectroscopy was employed under applied cathodic polarization. Moreover, a slow-strain rate test was conducted to evaluate loss of elongation (i.e., indicative of hydrogen embrittlement (HE)) and examine fracture surfaces. Results showed that the presence of a thin Zn-flash coating, even when it was not distributed uniformly, reduced hydrogen evolution rate and substantially impeded infusion of hydrogen into the steel substrate. This was primarily due to a hydrogen overvoltage on Zn coating and trapping of hydrogen at the interface of Zn coating/flash coating/steel substrate. Consequently, the sample with flash coating had a smaller HE index than the sample without flash coating. These results suggest that a thin Zn-flash coating could be an effective technical strategy for mitigating HE in advanced high-strength steels.

적층제조된 316L 스테인리스강 및 CoCrFeNi 중엔트로피 합금의 수소취화 거동 비교 (Comparative Study on the Hydrogen Embrittlement Behavior of Additively Manufactured 316L Stainless Steel and CoCrFeNi Medium-Entropy Alloy)

  • 정재영;정지윤;이동현
    • 열처리공학회지
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    • 제37권5호
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    • pp.237-246
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    • 2024
  • In this study, hydrogen embrittlement was investigated for 316L stainless steel (SS316L) and CoCrFeNi medium-entropy alloy (MEA) fabricated by laser-powder bed fusion. The in-situ hydrogen charging tensile tests revealed that the reduction in ductility due to hydrogen was more significant in the CoCrFeNi MEA, compared to the SS316L. In the case of SS316L, hydrogen-assisted cracks (HACs) were observed mainly on the surface, whereas in CoCrFeNi, cracks were found not only at the edges but also in the central region. HACs analysis confirmed that transgranular (TG) cracks were predominant in SS316L, whereas only intergranular cracks were formed in the CoCrFeNi MEA. The difference in hydrogen embrittlement resistance between SS316L and CoCrFeNi was discussed in terms of the differences in deformation microstructure and hydrogen diffusivity, as investigated through electron channeling contrast imaging and nanoindentation.

선박용 고강도 Al합금(5456-H116)의 최적 방식 전위결정에 관한 연구 (Investigation on optimum protection potential of high-strength Al alloy(5456-H116) for application in ships)

  • 김성종;고재용
    • Journal of Advanced Marine Engineering and Technology
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    • 제30권1호
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    • pp.157-168
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    • 2006
  • Recently, interest in using Al alloys in ship construction instead of fiber-reinforced plastic (FRP) has increased because of the advantages of A) alloy ships over FRP ships, including high speed, increased load capacity. and ease of recycling. This paper investigated the mechanical and electrochemical properties of Al alloys in a slow strain rate test under various potential conditions. These results will provide reference data for ship design by determining the optimum protection potential regarding hydrogen embrittlement and stress corrosion cracking. In general, Al and Al alloys do not corrode on formation of a film that has resistance to corrosion in neutral solutions. In seawater, however, $Cl^-$ ions lead to the formation and destruction of a Passive film. In a potentiostatic experiment. the current density after 1200 sec in the Potential range of $-0.68\~-1.5\;V$ was low. This low current density indicates the protection potential range. Elongation at an applied potential of 0 V was high in this SSRT. However, corrosion protection under these conditions is impossible because the mechanical properties are worse owing to decreased strength resulting from the active dissolution reaction in parallel parts of the specimen. A film composed of $CaCO_3\;and\;Mg(OH)_2$ confers corrosion resistance. However, at potentials below -1.6 V forms non-uniform electrodeposition coating, since there is too little time to form a coating. Therefore, we concluded that the mechanical properties are poor because the effect of hydrogen gas generation exceeds that of electrodeposition. Comparison of the maximum tensile strength, elongation, and time to fracture indicated that the optimum protection potential range was from -1.45 to -0.9 V (SSCE).

압력용기용 Cr-Mo강의 수소취화 특성 (The Characteristics of the Hydrogen Embrittlement for the Cr-Mo Steels in Use of Pressure Vessel)

  • 이휘원;양현태;김상태
    • 대한기계학회논문집A
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    • 제26권6호
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    • pp.1107-1113
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    • 2002
  • This study presents the hydrogen emblittlement in the metal, which decreases the ductility and then induces the brittle fracture. The contribution deals with the effect of strain rate and notch geometry on hydrogen emblittlement of 1.25Cr-0.5Mo and 2.25Cr-1Mo steels, which are in use at high pressure vessel. Smooth and notched specimens were examined to obtain the elongation and tensile strength. For charging the hydrogen in the metal, the cathodic electrolytic method was used. In this process, current density is maintained constant. The amount of hydrogen penetrated in the specimen was detected by the hydrogen determenator(LECO RH404) with the various charging time. The distribution of hydrogen concentration penetrated in the specimen was obtained by finite element analysis. The amount of hydrogen is high in smooth specimen and tends to concentrate in the vicinity of surface. The elongation and tensile strength decreased with the passage of charging time in 1.25Cr-0.5Mo and 2.25Cr-1Mo steels. The elongation increased and tensile strength decreased as strain rate increased. As a result of this study, it is supposed that 1.25Cr-0.5Mo steel is more sensitive than 2.25Cr-lMo steel in hydrogen embrittlement. Hydrogen embrittlement susceptibility of notched specimen after hydrogen charging is more remarkable than that of smooth specimen.

원자로 압력용기 원주방향 용접부의 가압열충격 심사기준온도의 적정성 평가

  • 장창희;정일성
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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    • pp.369-376
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    • 1998
  • 원자로 압력용기는 원자력발전소의 일차 압력경계를 구성하는 핵심 부품으로 이의 건전성은 원전의 안전성과 수명관리에 결정적인 영향을 미친다. 탄소강으로 구성된 압력용기는 노심에 근접하게 위치하여 운전중 계속되는 고속중성자 조사로 인하여 인성이 감소한다. 운전중 비상노심 냉각수가 주입되어 압력용기가 급격하게 냉각되면서 압력이 높게 유지되거나 재가압이 되는 가압열충격 현상이 발생하는 경우 조사취화된 압력용기가 적절한 안전여유를 가지지 못할 수도 있다. USNRC에서는 이에 대한 종합적인 연구결과를 바탕으로 가압열충격 규정을 제정하여 가압열충격 기준온도(RT$_{PTS}$)의 계산 방법과 심사기준온도를 제시하였다. 가압열충격 심사기준온도의 결정근거가 기술되어 있는 SECY 82-465에 의하면 축방향 용접부에 대한 위험도를 평가하여 270℉를 심사기준온도로 정하고 원주방향 용접부에 대해서는 30℉를 더하여 300℉를 심사기준온도로 제시하였다. 이 연구에서는 이렇게 제정된 원주방향 용접부에 대한 심사기준온도의 적정성을 평가하기 위하여 균열방향에 따른 가압열충격 위험도를 VISA-II 코드로 평가하였다. 우선 가압열충격 기준온도 제정 시 사용된 방법과 결과들을 검토하고 NRC의 계산결과를 재현하였다. 이를 바탕으로 원주방향 용접부에 대한 위험도를 평가한 결과 균열방향의 차이를 고려하기 위해 적용된 기술적 여유도인 30℉는 과도한 보수성을 내포하고 있음을 알 수 있었다. 원주방향 용접부가 축방향 용접부와 동일한 수준의 가압열충격 위험도를 가지기 위한 심사기준온도 차이는 50℉ 이상인 것으로 평가되었다.을 수 있었다.ngineering because this field has large uncertainties on predicting the effect of earthquake on structures. This paper is based on the presented paper at the Bertero Symposium held in January 31an4 February 1 at Berkeley, California, USA which was entitled "Needs to Evaluate Real Seismic Performance of Buildings-Lessons from 1995 Hyogoken-Nambu Earthquake-". The lessons for buildings from the damage due to the Hyogoken-Nambu Earthquake are necessity to develop more rational seismic design codes based upon a performance-based design concept, and to evaluate seismic performance of existing buildings. In my keynote lecture at the Korean Association for Computational Structural Engineering, the history of seismic design and use of structural analysis in Japan, the lessons for buildings from

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삼중수소 저장용기 이종용접부의 수소취화 거동 평가 (II) (Evaluations of Hydrogen Embrittlement Behaviours on Dissimilar Welding Part of SDS Bottles (II))

  • 조경원;최재하;장민혁;이영상;홍태환
    • 한국수소및신에너지학회논문집
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    • 제26권2호
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    • pp.120-126
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    • 2015
  • Recently, the ever-increasing use of fossil fuels for rapid industrial development and population significantly caused an environment pollution and global warming such as climate change. So research and development of sustainable and eco-friendly energy have been performed. Especially the interest in nuclear fusion fuel was significantly increased from the developed countries. The system of fusion energy production was tritium separation, storage and delivery, and purification. Republic of Korea is in charge of Storage and Delivery System (SDS) in the International Thermonuclear Experimental Reactor (ITER). Welding part of the SDS bottles for storing the tritium is known to be susceptible to hydrogen embrittlement. In this study, conducted a study for the relaxation of the stability and hydrogen embrittlement of the weld area. The hydrogen heat treatment was processed through the Pressure-Composition-Temperature (PCT) device according to the time variation. Also mechanical properties such as impact test and hardness test according to using the alkaline cleaning liquid for hydrogen embrittlement relief and the fracture was observed by scanning electron microscopy (SEM) after the mechanical properties evaluation.

삼중수소 저장용기 이종용접부의 수소취화 거동 평가 (I) (Evaluations of Hydrogen Embrittlement Behaviours on Dissimilar Welding Part of SDS Bottles (I))

  • 조경원;최재하;장민혁;이영상;홍태환
    • 한국수소및신에너지학회논문집
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    • 제26권2호
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    • pp.114-119
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    • 2015
  • Nowdays, fossil fuels have been used as an important resource in development of industry. But it is limited and caused climate change such as pollution and global warming. So nuclear fusion research is being issued with tritium to develop eco-friendly and sustainable energy. Republic of Korea is in charge of Storage and Delivery System (SDS) in the International Thermonuclear Experimental Reactor (ITER), weld present in the SDS bottles are easily exposed to the hydrogen embrittlement of special characteristics of the hydrogen in hydrogen atmosphere, When the hydrogen embrittlement is rapidly progresses, the cracking is generated in the weld zone. Due to this cracking, the risk of leakage of tritium into the atmosphere occurs. In this study, hydrogen heat treatment was processed through the Pressure-Composition-Temperature (PCT) device according to the time variation. Also mechanical properties such as rupture strength test, three point bend test and hardness test in accordance with the respective time have been conducted and the fracture was observed by scanning electron microscopy(SEM) after the mechanical properties evaluation.

페라이트계 스테인리스강 용접부 특성에 미치는 보호가스 조성의 영향 (Effects of Shielding Gas Composition on the Properties of Ferritic Stainless Steel GTA weld)

  • 이원배;유한진;김호수
    • 대한용접접합학회:학술대회논문집
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    • 대한용접접합학회 2010년도 춘계학술발표대회 초록집
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    • pp.20-20
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    • 2010
  • GTA (Gas Tungsten Arc)용접은 불활성 분위기에서 용접이 이루어지기 때문에 타 아크용접법에 비해 용접부 품질이 우수하여 고품질이 요구되는 산업분야에 널리 이용되고 있다. 하지만 스테인리스강으로 pipe를 제조하기 위해 GTA 용접을 적용할 경우, Laser 및 고주파 용접 (HFIW)에 비해 용접부 품질 및 용접속도가 낮기 때문에 pipe를 제조하는 산업에서 적용에 제한을 받고 있다. 하지만, GTA는 laser 혹은 HFIW에 비해 가격이 1/10수준으로 낮고, 용접부 gap tolerance 및 용접면 관리범위가 넓은 장점이 있기 때문에 GTA의 용접속도 및 용접품질을 향상시키기 위한 연구가 꾸준히 진행되고 있다. 일반적으로 스테인리스강 GTA용접 시 용접속도를 향상시키기 위해, 모재의 성분 제어 (합금성분 최적화-Al, S, Se, O등), Flux 도포 기술 (산화물을 용접전에 도포하여 용접속도 향상) 및 혼합보호가스 적용 등이 있다. 스테인리스강 용접 시 보호가스로는 용접부 품질을 확보하기 위해 Ar을 주로 사용하고 있다. 하지만 용입 특성을 향상시키기 위해 아크의 온도를 높일 수 있는 He, 혹은 $H_2$ gas를 단독 혹은 혼합하여 사용하고 있다. 오스테나이트계 스테인리스의 경우 용입특성을 향상시키기 위해 Ar에 $H_2$를 2~10%정도 혼합하여 사용하고 있다. 페라이트계 스테인리스강은 수소에 대한 고용도가 상대적으로 작아 용접부 수소 취화를 일으킬 수 있기 때문에 적용에 제한을 받고 있어 그 대안으로 산소를 극히 소량을 혼합하여 용입성 향상에 대한 연구가 보고 되고 있다. 따라서 본 연구에서는 페라이트계 스테인리스강의 용입특성을 향상시킬 목적으로 Ar에 산소를 미량 첨가 (1%미만) 하여 용접전류 및 산소 함량에 따른 용입특성의 변화에 대해 연구하였다. 또한 기계적인 물성 및 부식특성을 평가하였고, 최종적으로 실용화 가능성을 파악하기 위해 용접전극의 수명 테스트를 실시하였다. 실시한 결과, 산소가 첨가량 증가 할수록 용입특성은 상승하였으며, 기계적인 물성 또한 산소를 첨가하지 않은 경우에 비해 거의 유사한 값을 얻을 수 있었다, 하지만 산소함량이 증가 할수록 전극의 수명은 감소하여 교체주기가 증가함을 알 수 있다. 본 연구를 통해 얻어진 기술을 상용화시키기에는 극복해야할 문제가 있지만, 소재 합금성분 설계 시 용접생산성 향상위한 산소성분 범위를 제시할 수 있으리라 판단된다.

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중수로 압력관 재료의 조사 열화에 따른 인장거동 특성 (Tensile Behavior Characteristics of CANDU Pressure Tube Material Degraded by Neutron Irradiations)

  • 안상복;김영석;김정규
    • 대한기계학회논문집A
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    • 제26권1호
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    • pp.188-195
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    • 2002
  • To investigate the degradation of mechanical properties induced mainly by neutron irradiation, the tensile tests were conducted from room temperature to 300\\`c using the irradiated and the unirradiated Zr-2.5Nb pressure tube materials. The irradiated longitudinal and transverse specimens were collected from the coolant inlet, middle, and outlet parts of M-11 tube which had been operated in Wolsung CANDU Unit-1 and exposed to different operating temperatures and irradiation fluences. The different tensile behavior was characterized not by the fluences of irradiation but by the tensile loading direction. The transverse specimen showed the higher strength and lower elongation than those of the longitudinal one. It was believed that these phenomena resulted from the microstructure anisotropy caused by the extrusion process. The increased strength hardening and decreased elongation embrittlement of the irradiated material were compard to those of the unirradiated one. While the tensile strength of the inlet was higher than that of the outlet, the elongation of the inlet was lower than that of outlet. Considering the operation condition, it was proposed that the operating temperature could be a more effective parameter than the irradiation fluence for long-time life. Through the TEM observation, it was found that while the a-type dislocation density was increased, the c-type dislocation was not changed in the irradiated. The fact that the higher dislocation density was sequentially distributed over the inlet, the middle, and the outlet parts was consistent with the distribution of the tensile strength.

순 타이타늄의 GTAW 용접성 및 기계적 특성 (The weldability and mechanical property of CP titanium by GTAW)

  • 홍재근;김지훈;이채훈;염종택;강정윤
    • 대한용접접합학회:학술대회논문집
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    • 대한용접접합학회 2009년 추계학술발표대회
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    • pp.57-57
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    • 2009
  • 산업의 고도화에 따른 구조물의 사용 환경이 열악해지고 최근 에너지저감과 환경문제 개선을 위한 경화의 요구에 따라 뛰어난 내식성 및 우수한 고비강도 특성을 갖고 있는 타이타늄 및 타이타늄합금의 활용에 대한 연구가 많은 주목을 받고 있다. 이에 따라 타이타늄 신합금의 개발뿐만 아니라 기존에 개발되어 비교적 보편적으로 적용되고 있는 타이타늄 부품의 제조 및 성형기술에 대한 수요도 급증하고 있다. 특히, 기기 및 부품 제조를 위한 용접/접합기술도 매우 중요한 요소기술로 자리메김하고 있다. 타이타늄은 산소, 수소 등의 침입형 원소와의 친화력이 강한 활성이 큰 금속으로 용접시 고온에 노출되면 급격히 산화 및 취화 등의 문제를 발생한다. 따라서 타이타늄의 용접시에는 $426^{\circ}C$이상의 온도에서는 대기로부터 용접부가 차단되도록 하는 쉴딩기술이 매우 중요하다. 타이타늄의 용접은 일반적으로 아크용접, 전자빔 용접, 레이저 용접 및 확산접합 등이 적용되고 있으나 용접입열 조정이 용이하고 아크 안정성이 높고 용접부의 기계적 특성이 우수한 GTA 용접이 작업성을 고려하여 가장 많이 적용되고 있다. 본 연구에서는 미국용접학회(AWS)의 타이타늄 용접가이드를 분석 및 소개하였고, 1t 이하의 박판 CP Ti를 대상으로 GTAW 용접부 미세조직 및 기계적 특성을 분석하였다. 이때, 용접 비드폭 제어 및 펄스 용접기술을 통하여 박판 타이타늄의 최적 GTAW 공정변수 제어기술을 분석하였다.

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