• International Journal of Ocean Engineering and Technology Speciallssue:Selected Papers
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• 제6권1호
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• pp.69-74
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• 2003

Recent deepwater offshore structures in the Gulf of Mexico utilize butt welded tubular joints. Application of a welded tubular joint includes tendons, production risers, and steel catenary risers. Fatigue life assessment of these joints becomes more critical, as the structures to which they are attached are allowed to undergo cyclic and sometimes large displacements around an anchored position. Estimation of the fatigue behavior of these tubular members in the design stage is generally conducted by using S-N curves, as specified in the codes and standards. Applying the stress concentration factor of the welded structure to the S-N approach often results in a very conservative assessment, because the stress field acting on the tubular has a non-uniform distribution through the thickness. Fatigue life analysis using fracture mechanics has been applied in the design of the catenary risers. This technology enables the engineer to establish proper requirements on weld quality and inspection acceptance criteria to assure satisfactory structural integrity during its design life. It also provides guidance on proper design curves and a methodology for accounting for the effects of non-uniform stress distribution through the wall thickness. Still, there is inconsistency when designing tubular joints using a conventional S-N approach and when specifying weld flaw acceptance criteria using fracture mechanics approach. This study developed fatigue curves that are consistent with both the S-N approach and the fracture mechanics approach. Accounting for non-uniform stress distribution and threshold stress intensity factor were key parameters in relating both approaches. A series of S-N curves, generated from the fracture mechanics approach, were compared to the existing S-N curves. For flat plate butt joint, the S-N curve generated from fracture mechanics matches with the IIW class 100 curve when initial crack depth was 0.5 mm (0.02). The new curves for tubular joint agree very well with the experimental results. The comparison also indicated the degree of conservatism built into the API X design curve.

• 한국가스학회지
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• 제12권1호
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• pp.13-18
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• 2008

지진 및 외부 진동에 의하여 구조물에 발생하게 되는 진동량은 진동 속도와 피해규모가 비례하는 관계에 있음을 고려하여 일반적으로 진동속도로 나타내어진다. 본 연구에서는 진동 속도 기반의 구조물 진동기준을 검토하고, 이를 고려하여 도로 하부 매설 가스 강관의 안정성 평가를 수행하였다. 가스공사 주사용 배관인 762 mm API 5L Gr. X65 강관을 해석 대상 배관으로 선정하였으며 도로설계기준에 의하여 지반 매설 조건 및 DB-24 하중을 다양한 속도에 대한 시간 함수로 고려하여 재하하였다. 진동속도는 차량 진행 속도 80 km/h까지 증가하다가 이후 감소하는 경향을 보였으며, 차량 진행 속도 80 km/h에서 0.034 cm/s의 진동 속도를 보임으로서 진동 기준 대비 매우 작은 값임을 확인하였다. 또한 감쇄법칙을 적용하여 진행파의 속도를 분석한 결과, 차량 진행 속도 80 km/h에서 가장 작은 속도를 나타내었다.

• 대한기계학회논문집A
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• 제34권9호
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• pp.1273-1279
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• 2010

가압중수로 연료관은 CSA N 285.4 기술기준에 따라 주기적인 가동중검사가 수행되고 있다. 가동중검사시 발견된 결함이 CSA N 285.4 의 허용기준을 초과하는 경우, 결함 연료관의 계속 운전을 위해 가동적합성 평가를 허용하고 있다. 캐나다 COG(CANDU Owner's Group)를 중심으로 중수로 연료관의 결함 건전성 평가 기술기준인 CSA N285.8 이 개발되었다. 본 논문에서는 CSA N285.8 을 기반으로 연료관의 건전성 평가시스템 WIES(Wolsong In-service Evaluation System)를 개발 하였다. 중수로 연료관의 가동중검사시 결함이 발견되는 경우, 개발된 시스템은 신속하고 정확한 건전성 평가를 수행하여 계획예방 정비기간의 연장을 방지하여 원전 이용률 향상에 기여할 것으로 판단된다.

• 대한기계학회논문집A
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• 제31권2호
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• pp.277-284
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• 2007

The steam generator in a nuclear power plant is a large heat exchanger that uses heat from a reactor to generate steam to drive the turbine generator. Rupture of a steam generator tube can result in release of fission products to environment outside. Therefore, an accurate integrity assessment of the steam generator tubes with cracks is of great importance for maintaining the safety of a nuclear power plant. The steam generator tubes are supported at regular intervals by support plates and rotations of the tubes are restrained. Although it has been reported that the limit load for a circumferential crack is significantly affected by boundary condition of the tube, existing limit load solutions do not consider the restraining effect of support plate correctly. In addition, there are no limit load solutions for circumferential cracks in U-bend region with the effect of the support plate. This paper provides detailed limit load solutions for circumferential cracks in top of tube sheet and the U-bend regions of the steam generator tube with the actual boundary conditions to simulate the restraining effect of the support plate. Such solutions are developed based on three dimensional finite element analyses. The resulting limit load solutions are given in a polynomial form, and thus can be simply used in practical integrity assessment of the steam generator tubes.

• Journal of Astronomy and Space Sciences
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• 제36권1호
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• pp.35-43
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• 2019

The Optical Wide-field patroL-Network (OWL-Net) is a global optical network for Space Situational Awareness in Korea. The primary operational goal of the OWL-Net is to track Low Earth Orbit (LEO) satellites operated by Korea and to monitor the Geostationary Earth Orbit (GEO) region near the Korean peninsula. To obtain dense measurements on LEO tracking, the chopper system was adopted in the OWL-Net's back-end system. Dozens of angle-only measurements can be obtained for a single shot with the observation mode for LEO tracking. In previous work, the reduction process of the LEO tracking data was presented, along with the mechanical specification of the back-end system of the OWL-Net. In this research, we describe an integrity assessment method of time-position matching and verification of results from real observations of LEO satellites. The change rate of the angle of each streak in the shot was checked to assess the results of the matching process. The time error due to the chopper rotation motion was corrected after re-matching of time and position. The corrected measurements were compared with the simulated observation data, which were taken from the Consolidated Prediction File from the International Laser Ranging Service. The comparison results are presented in the In-track and Cross-track frame.

• 한국소프트웨어감정평가학회 논문지
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• 제15권2호
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• pp.9-16
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• 2019

한국저작권위원회에 의뢰된 소프트웨어 저작물 감정 대상 중 25% 이상은 소프트웨어 완성도-하자 감정이다. 기존 소프트웨어 완성도-하자 감정 사례의 대부분은 해당 소프트웨어의 기능성에 국한하여 계약서에 포함된 또는 고객이 원하는 요구사항들이 구현되어 작동되는지 확인하는 방식으로 이루어졌다. 본 논문은 소프트웨어 완성도 정의에 부합할 수 있도록, 보다 체계적이고 합리적인 완성도-하자 감정 기법을 제안한다. ISO/IEC 9241.10 표준은 소프트웨어 품질 제고를 위한 설계표준이라 할 수 있다. ISO/IEC 9241.10 표준은 준수되어야 하는 7개 항목을 규정하고 있으며, 작업을 위한 기능상의 완전성과 작업 능률 효율화를 위한 사용상의 완전성을 요구하고 있다. 본 논문에서 제시된 소프트웨어 완성도-하자 감정 방법론은 소프트웨어의 질적 품질에 대한 완성도 감정으로 기존 기능구현-작동 여부 감정 방법론은 보완하고 있다.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2011년도 정기총회 및 추계학술대회 논문집
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• pp.707-710
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• 2011

System safety is defined as the state where the hazard risks due to internal system, interface, operation and maintenance are controlled as acceptable levels. It is represented and evaluated either with the risk level of each risk factor with the consideration of operation environments or with Safety Integrity Level (SIL) which is the system functional safety without considering application environments. The assessment results are issued in forms of certificates and they are reused in many cases. However, the conditions and restrictions for different application environments vary in each case, therefore, additional evaluation on the preconditions of assessment in comparison with the actual application environment must be carried out. For the area of train control, TR 50506-1 has been established based on the IEC 62425 (international standard for safety of train control system by RSSB) and EN 50129 (Europe standard) for the further assessment. In this paper, the analysis on TR 5056-1 has been conducted in depth. The purpose of the study is to determine the requirements for inter-acceptability including scope, procedures, principles, examination and suitability. The results can be utilized for the system safety maintenance when new devices or components are introduced in conventional systems.

• Wind and Structures
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• 제13권1호
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• pp.1-20
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• 2010

The recommended factored design wind load effects for overhead lattice transmission line towers by codes and standards are evaluated based on the applicable wind load factor, gust response factor and design wind speed. The current factors and design wind speed were developed considering linear elastic responses and selected notional target safety levels. However, information on the nonlinear inelastic responses of such towers under extreme dynamic wind loading, and on the structural capacity curves of the towers in relation to the design capacities, is lacking. The knowledge and assessment of the capacity curve, and its relation to the design strength, is important to evaluate the integrity and reliability of these towers. Such an assessment was performed in the present study, using a nonlinear static pushover (NSP) analysis and incremental dynamic analysis (IDA), both of which are commonly used in earthquake engineering. For the IDA, temporal and spatially varying wind speeds are simulated based on power spectral density and coherence functions. Numerical results show that the structural capacity curves of the tower determined from the NSP analysis depend on the load pattern, and that the curves determined from the nonlinear static pushover analysis are similar to those obtained from IDA.

• 한국소음진동공학회논문집
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• 제23권4호
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• pp.308-314
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• 2013

The vibration and stress analysis program of comprehensive vibration assessment program(CVAP) is to theoretically verify the structural integrity of reactor vessel internals(RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the applicability of the vibration and stress analysis method of APR1400 RVI CVAP. The analysis method was developed to use 3-dimensional detail hydraulic and structural models with ANSYS and CFX. To assess the method, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the measured data in the OPR1000 RVI CVAP. The results predicted with this method were close to the measured values considerably. Therefore, the analysis method was developed properly.

• Journal of Welding and Joining
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• 제24권2호
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• pp.48-56
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• 2006

The fatigue strength of the welds is affected by such factors as the weld geometry, microstructures, tensile properties and residual stresses caused by fabrication. It is very important to evaluate the structural integrity of the welds in nuclear power plant because the weldment undergoes the most of damage and failure mechanisms. In this study, the fatigue assessments for a reactor vessel outlet nozzle with the weldment to the piping system are performed considering the welding residual stresses as well as the effect of local brittle zone in the vicinity of the weld fusion line. The analytical approaches employed are the microstructure and mechanical properties prediction by semi-analytical method, the thermal and stress analysis including the welding residual stress analysis by finite element method, the fatigue life assessment by following the ASME Code rules. The calculated results of cumulative usage factors(CUF) are compared for cases of the elastic and elasto-plastic analysis, and with or without residual stress and local brittle zone effects, respectively. Finally, the fatigue life of reactor vessel outlet nozzle weld is slightly affected by the local brittle zone and welding residual stresses.