• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.264-267
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• 2004

Wall thinning of carbon steel pipe components due to Flow-Accelerated Corrosion (FAC) is one of the most serious threats to the integrity of steam cycle piping systems in Nuclear Power Plants (NPP). Since the mid-1990s, secondary side piping systems in Korean NPPs have experienced wall thinning, leakages and ruptures caused by FAC. Korea Electric power Research Institute (KEPRI) and Korea Hydro & Nuclear Power Co., LTD. (KHNP) have conducted a study to develop the methodology for systematic pipe management and established the Korean Thinned Pipe Management Program (TPMP). To effectively maintain the integrity of piping system, FAC engineer should understand the criterions of the structural integrity evaluation and the safety margin assessment for the thinned pipe component. This paper describes the technical items of TPMP, and shows the example of the integrity evaluation and safety margin assessment for three thinned pipe component of a NPP.

• 대한기계학회논문집A
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• 제36권9호
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• pp.1087-1094
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• 2012

본 논문에서는 구조 시험과 유한요소해석을 통하여 소형 풍력발전용 복합재 블레이드의 구조적 안전성을 평가하였다. 먼저, 선행연구에서 공력해석을 수행하여 정격 및 극한 풍속일 때의 블레이드가 받는 굽힘 모멘트를 산출하였다. 이를 이용하여 소형풍력발전기 관련 국제 규격인 IEC 61400-2에 따른 실규모 구조 시험을 수행하여 구조적 안전성을 평가하였다. 그리고 유한요소법을 이용한 구조 해석을 수행하여 구조 시험 결과와 비교하여 이의 정확성을 판단하였다. 또한, 구조 시험을 통해 블레이드에 대한 과잉 설계가 확인되었으며 이의 해결을 위하여 블레이드의 적층 순서 및 두께를 재선정하여 구조적 안전성을 평가하였다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2012년도 추계학술대회 논문집
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• pp.745-746
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• 2012

• 대한전기학회:학술대회논문집
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• 대한전기학회 2009년도 제40회 하계학술대회
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• pp.1441_1441
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• 2009

This paper describes performance of sealing integrity and bending strain of HV polymeric bushing with thermal mechanical test. Generally the properties of FRP tube can be influenced by the winding angle, wall thickness and winding tension. As a results, multi winding bushing shows that it has max deflection in the range of 16.5~16.9 mm.

• Journal of Mechanical Science and Technology
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• 제17권10호
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• pp.1475-1484
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• 2003

The EDM processing characteristics of one of the nickel-based heat resistant alloys, Hastelloy- X, were investigated under the various EDM conditions and analyzed in terms of surface integrity. This alloy is commonly used as a material for the hot gas path component of gas turbines and it is difficult to machine by conventional machining methods. The primary EDM parameter which was varied in this study were the pulse-on time. Since the pulse-on time is one of the main factors that determines the intensity of the electrical discharge energy, it was expected that the machining ratio and the surface integrity of the specimens would be proportionally dependent on the pulse-on duration. However, experimental results showed that MRR (material removal rate) and EWR (electrode wear rate) behaved nonlinearly with respect to the pulse duration, whereas the morphological and metallurgical features showed rather a constant trend of change by the pulse duration. In addition the heat treating process affected the recast layer and HAZ to be recrystallized but softening occurred in recast layer only. A metallurgical evaluation of the microstructure for the altered material zone was also conducted.

• Journal of Mechanical Science and Technology
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• 제20권12호
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• pp.2061-2078
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• 2006

The main purpose of this paper is to establish the high temperature structural integrity evaluating procedures for the next generation reactors, which are to be operated at over 500$^{\circ}C$ and for 60 years. To do this, comparison studies of the high temperature structural design codes and assessment procedures such as the ASME-NH (USA), RCC-MR (France), DDS (Japan), and R5 (UK) are carried out in view of the accumulated inelastic strain and the creep-fatigue damage evaluations. Also the application procedures of the ASME-NH rules with the actual thermal and structural analysis results are described in detail. To overcome the complexity and the engineering costs arising from a real application of the ASME-NH rules by hand, all the procedures established in this study such as the time-dependent primary stress limits, total accumulated creep ratcheting strain limits, and the creep-fatigue damage limits are computerized and implemented into the SIE ASME-NH program. Using this program, the selected high temperature structures subjected to two cycle types are evaluated and the parametric studies for the effects of the time step size, primary load, number of cycles, normal temperature for the creep damage evaluations and the effects of the load history on the creep ratcheting strain calculations are investigated.

• 대한금속재료학회지
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• 제49권8호
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• pp.589-595
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• 2011

Laminated glass fiber-reinforced plastic (GFRP) composites were applied to an insulating structure of a magnet system for a nuclear fusion device. Decreased inter-laminar strength by a strong repulsive force between coils which is induced a problem of structural integrity in laminated GFRPs. Therefore, it is important to investigate the inter-laminar characteristics of laminated GFRP composites in order to assure more reliable design and better structural integrity. Three types of the laminated GFRP composites using a high voltage insulating materials were fabricated according to each molding process. To evaluate the grade of the fabricated composites, mechanical tests, such as hardness, tensile and compressive tests,were carried out. The autoclave molding composites satisfied almost of the mechanical properties reguested at the G10 class standard, but the vacuum impregnation (VPI) and Prepreg composites did not.

• 대한기계학회논문집A
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• 제37권1호
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• pp.9-16
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• 2013

최근 환경적 요인으로 친환경 에너지나 효율성이 높은 에너지관리 기술에 관한 많은 연구가 진행되고 있다. 그 중에서 열교환기는 역사가 오래된 기계장치 이지만 최근 온실가스 저감을 위해 항공기 등에 응용을 시도함에 따라 그 가치가 증가하고 있다. 또한 이러한 열교환기가 항공기 엔진에 적용될 경우 고온, 고압의 조건을 견디어야 함으로 기계적 건전성 평가는 매우 중요하다. 따라서 본 연구에서는 관형 열교환기의 취약부인 브레이징 접합부의 국부적인 물성분포 분석과 유체-고체 연성해석을 통하여 구조적 안전성을 평가하였다. U자형 단일 곡관을 제작하여 해석과 실험을 통하여 신뢰성을 검증하였고 브레이징 조건 변경을 통하여 재료 분포를 확인하였다.

• 한국안전학회지
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• 제22권4호
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• pp.7-12
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• 2007

In order to evaluate the integrity of Zr-2.5Nb pressure tubes, probabilistic fracture mechanics(PFM) approach was employed. Failure assessment diagram(FAD), plastic collapses, and critical crack lengths(CCL) were used for evaluating the failure probability as failure criteria. The Kr-FAD as failure assessment diagram was used because fracture of pressure tubes occurred in brittle manner due to hydrogen embrittlement of material by deuterium fluence. The probabilistic integrity evaluation observed AECL procedures and used fracture toughness parameters of EPRI and recently announced theory. In conclusion, the probabilistic approach using the Kr-FAD made it possible to determine major failure criterion in the pressure tube integrity evaluation.

• 대한기계학회논문집A
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• 제29권5호
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• pp.734-742
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• 2005

The present study proposes the integrity evaluation model for a straight pipe with local wall thinning defect, which reflects the characteristics of training shape and loading condition in the Piping of nuclear power plant. For this purpose, a series of finite element analyses are performed under various defect geometries and loading conditions, and real pipe experiment data performed previously is employed. The model includes the effect of thinning length as well as thinning depth and width, and also it considers the combined loading effect between internal pressure and bending moment. The proposed model has been validated using the results of finite element analysis and pipe experiment data. The results indicate that the proposed model provides more reliable predictions of pipe failure than the current existing model, in terms of accuracy, consistency, and conservativeness of results.