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      • 용접잔류응력을 고려한 PWSCC 결함성장평가

        윤은섭(Yun Eun Sub),나경환(Na Kyung Hwan),박영섭(Park Young Sheop) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11

        In nuclear power plants, nickel base alloys that have high corrosion resistance and good mechanical properties have been used in tubes, small bore penetrations and dissimilar metal weld materials. But, since 2000, several PWSCC (Primary Water Stress Corrosion Cracking) occurrences have been reported worldwide in various pressure boundary components. PWSCC is the mechanism that forms cracks in susceptible materials in the presence of a corrosion environment and tensile stresses. If the materials and environments are fixed, PWSCC characteristics are mainly determined by tensile stresses. In this paper, PWSCC growth assessment of nickel base alloy dissimilar metal welds are introduced. To calculate the total stress, the operating stress and weld residual stress are considered. The FEA (Finite Element Analysis) method is applied to calculate the weld residual stress, and finally PWSCC growth rate is calculated.

      • KCI등재

        외면 보수 용접이 원전 고온관 밀림노즐에서의 결함성장에 미치는 영향

        나경환,윤은섭,박영섭,Na, Kyung-Hwan,Yun, Eun-Sub,Park, Young-Sheop 대한용접접합학회 2011 대한용접·접합학회지 Vol.29 No.2

        Nickel-based austenitic alloys such as Alloy 82 and 182 had been employed as the weld metals in nuclear power plants (NPPs) due to their high corrosion resistance as well as good mechanical properties. However, since the 2000s, the occurrence of primary water stress corrosion cracking has been reported in conjunction with these alloys in domestic and oversea NPPs. In the present work, we assumed an imaginary crack at the inner surface of a surge nozzle weld that had previously experienced the outside repair welding, and constructed its finite element model. Finite element analysis was performed with respect to the heat transfer, and then to the residual stress for obtaining the total applied stress distributions. These stress distributions were finally converted to the stress intensity factors for estimating crack growth rate. From the comparison of crack growth rate curves for the cases of no repair welding and outside repair welding, it was found that the outside repair welding did not exhibit negative effect on the crack growth for the surge nozzle under consideration in this work; in both cases, the cracks stopped growing before they became the through-wall cracks.

      • KCI등재후보

        국제공동연구 PARTRIDGE를 통한 확률론적 건전성 평가 기술 개발 현황

        김선혜,박정순,김진수,이진호,윤은섭,양준석,이재곤,박홍선,오영진,강선예,윤기석,박재학,Kim, Sun Hye,Park, Jung Soon,Kim, Jin Su,Lee, Jin Ho,Yun, Eun Sub,Yang, Jun Seog,Lee, Jae Gon,Park, Hong Sun,Oh, Young Jin,Kang, Sun Yeh,Yoon, Ki Seok,P 한국압력기기공학회 2013 한국압력기기공학회 논문집 Vol.9 No.1

        A probabilistic assessment code, PRO-LOCA ver. 3.7 which was developed in an international co-operative research program, PARTRIDGE was evaluated by conducting sensitivity analysis. The effect of some variables such as simulation methods (adaptive sampling, iteration numbers, weld residual stress model), crack features(Poisson's arrival rate, maximum numbers of cracks, initial flaw size, fabrication flaws), operating and loading conditions(temperature, primary bending stress, earthquake strength and frequency), and inspection model(inspection intervals, detectable leak rate) on the failure probabilities of a surge line nozzle was investigated. The results of sensitivity analysis shows the remaining problems of the PRO-LOCA code such as the instability of adaptive sampling and unexpected trend of failure probabilities at an early stage.

      • KCI등재

        프라마톰형 원전의 배관 가동중검사에 리스크 정보를 활용한 기법 적용

        김진회(Jin-Hoi Kim),이정석(Jeong-Seok Lee),윤은섭(Eun-Sub Yun) 한국비파괴검사학회 2014 한국비파괴검사학회지 Vol.34 No.4

        가압경수로형 원자력발전소 소유자 그룹은 ASME Sec. XI 코드의 배관 샘플링검사법 대안으로 리스크 정보를 활용한 가동중검사 프로그램(RI-ISI)을 개발 및 적용하였다. RI-ISI 프로그램은 파손 메커니즘이 있는 고위험도 배관에 검사를 집중함으로써 발전소의 전반적인 안정성을 향상시켰다. 또한, RI-ISI 프로그램은 비파괴검사 물량, 검사자 방사선 피폭, 검사 시간 등을 줄일 수 있다. 배관 RI-ISI 방법은 한국 표준형 원자력발전소 3개호기에 적용되고 있으며 다른 발전소도 개발중에 있다. 이 논문에서는 프라마톰형(프랑스형) 원전에 대한 RI-ISI 방법을 연구하고 그 결과를 나타내었다. 프라마톰형 원전에 대한 RI-ISI 적용은 발전소 안전성을 향상시키고 유지시키며 계량화할 수 없는 이익을 준다는 결론에 도달하였다. The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI" sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

      • KCI등재

        고에너지 전자빔 투사방법으로 제조된(TiC, SiC)/Ti-6Al-4V 표면복합재료의 미세조직과 마모 및 파괴특성(1. 미세조직 형성과정)

        오준철,윤은섭,이성학 대한금속재료학회 2002 대한금속·재료학회지 Vol.40 No.11

        The present study is concearned with microstructural analysis of (TiC, SiC)/Ti-6Al-4V surfaces composites fabricated by high-energy electron beam irradiation. The mixtures of TiC, SiC, Ti+SiC, and TiC+SiC powders and CaF_2 flux were evenly deposited on a Ti-6Al-4V substrate, and then electron beam was irradiated on these mixtures using an electron beam accelerator. In the specimens processed with flux addition, the surface-alloyed layers of 1.2∼2.1 ㎜ in thickness were homogeneously formed without defects, and contained a large amount (30∼66 vol.%) of precipitates such as TiC and Ti_5Si_3 in the martensitic matrix. Upon electron beam irradiation, (TiC, SiC)/flux powder mixtures and part of the substrate were melted to form a molten metal containing Ti, Si, and C. Here, C and Si atoms interacted with Ti atoms to form TiC and Ti_5Si_3, respectively, and the matrix was composed of martensite because of fast cooling during solidification. Microstructural modifications including melting, solidification, precipitation, and phase transformation processes could be explained well from a Ti-Si-C ternary phase diagram.

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