• Transactions of the Korean Society of Mechanical Engineers A
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• v.23 no.7 s.166
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• pp.1147-1154
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• 1999

The objective of this paper is to evaluate the fracture resistance characteristics of SA508 CL.1a carbon steel, and their associated welds manufactured for primary coolant piping system of nuclear power plants. The effect of various parameters such as pipe size, welding method and chemical composition on the material properties were discussed. Test results showed that the offset of pipe size on tincture toughness was negligible, while the effect of welding method on fracture toughness was significant. In addition, Fracture toughness for carbon steel was influenced by silicon contents due to the different steel refining processes.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.275-282
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• 1996

일체형 원자로는 증기발생기 및 가압기를 압력용기 내에 설치한 것으로서 연결배관이 없기 때문에 배관의 파단에 의한 대형 냉각재 상실사고를 근원적으로 배제하고 전체계통을 단순화 시킬 수 있다. 증기발생기는 대부분 관류식으로서 일체식과 모듈식이 사용되고 있다. 본 연구에서는 모듈식 나선형 증기발생기를 사용한 일체형 신형경수로의 예비 개념설계를 수행하였다. 가압기는 원자로 내에 별도의 용기를 설치하는 내장형 자기가압기를 채택하였다. 제어봉 구동장치는 핵분열 반응열을 이용한 원자로 기동을 위하여 반응도를 미세하게 조정하는 것이 가능하고 지진하중과 같은 동하중의 영향을 최소화하기 위하여 원자로용기 외부로의 돌출부분을 최소화하는 설계개념을 채택하였다. 냉각재 펌프는 Canned Motor Pump를 원자로용기 상부에 수직으로 직접 부착하는 개념을 사용하였다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.25 no.8
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• pp.1235-1241
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• 2001

An engineering estimation equation for the crack opening displacement(COD) is proposed for a complex cracked pipe, based on the reference stress approach. To define the reference stress, a simple plastic limit load analysis for the complex cracked pipe subjected to combined bending and tension is performed considering the crack closure effect in the compressive-stressed region. Comparison with ten published test data and the results from existing method shows that the present method not only reduces non-conservatism associated with the existing method, but also provides consistent and overall satisfactory results.

• Computational Structural Engineering
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• v.8 no.1
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• pp.13-18
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• 1995

원전의 주요 구조물은 극심한 재해를 초래할 수 있는 자연현상(지진, 쓰나미 등)이 수반하는 극한하중에 견딜 수 있어야 하고 내부의 안전관련 기기의 기능과 만일의 사고(주증기나 고에너지 배관파단사고)시에도 구조적 안전성이 보장되도록 설계.시공되고 있다. 또한 운전원의 조작실수나 오판을 극복할 수 있도록 원자로 고유의 안전성과 자연법칙에 의한 정상유지를 할 수 있는 신기술이 도입되고 있다. 품질보증 계획에 의한 최선의 품질보장, 엄격한 방사선 감시와 온배수 영향의 최소화, 최신방사성 폐기물 처분기술 적용 등을 통하여 기술의존형 에너지인 원자력의 활용증대가 불가피하다고 판단된다.

• Proceedings of the KWS Conference
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• 2004.05a
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• pp.149-151
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• 2004

고효율, 대용량의 친환경적이며 경제적인 발전소건설을 위해 초초임계압(USC: Ultra Super Critical) 석탄화력발전소의 건설이 세계적인 추세이다. 이러한 USC발전소는 효율향상을 위해 증기온도와 압력의 상승, 경제적 운용을 위해 부하변동운전 적용확대가 필수적이다. (중략)

• Transactions of the Korean Society of Mechanical Engineers A
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• v.39 no.5
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• pp.453-460
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• 2015

Since the Fukushima nuclear accident, several researchers are extensively studying the effect of torsion on the piping systems In nuclear power plants. Piping installations in power plants with a circumferential crack can be operated under combined loading conditions such as bending and torsion. ASME Code provides flaw evaluations for fully plastic fractures using limit load criteria for the structural integrity of the cracked pipes. According to the recent version of Code, combined loadings are provided only for the membrane and bending. Even though actual operating conditions have torsion loading, the methodology for evaluating torsion load is not established. This paper provides the results of limit load analyses by using finite element models for circumferentially cracked pipes under pure bending, pure torsion, and combined bending and torsion with tension. Theoretical limit load solutions based on net-section fully plastic criteria are suggested and verified with the results of finite element analyses.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.42-48
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• 2020

The effect of improving the tensile and J-R fracture toughness properties of SA508 Gr.1a on the LBB margin for the main steam pipe is investigated. The material properties and microstructure images of the existing main steam piping material SA106 Gr.C used in domestic nuclear power plants and the newly selected material SA508 Gr.1a were compared. For each material, LBB margins were calculated and compared through finite element analysis and crack instability evaluation. The LBB margin of the improved SA508 Gr.1a is found to be greatly improved compared to that of the existing SA106 Gr.C and SA508 Gr.1a. This is because of the increased material's strength and J-R fracture toughness compared to the previous materials. In order to analyze the effect of physical property change on the LBB margin, the sensitivity of each LBB margin according to the variation of tensile strength and J-R fracture toughness was analyzed. The effect of the change in tensile strength was found to be greater than that of the change in fracture toughness. Therefore, an increase in strength significantly influenced the improvement of the LBB margin of the improved SA508 Gr.1a.

• Journal of the Korean Institute of Gas
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• v.22 no.3
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• pp.1-6
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• 2018

Reliability based design and assessment (RBDA) methodology is one of the newest directions of natural gas pipeline design method. Reliability targets are used to ensure that safety levels are met relevant limit states in the stage of design and maintenance. The target reliability for ultimate limit states such as large leak and rupture were developed using tolerable risk criteria for individual and societal risk. This paper shows the reliability target can be met through the implementation of periodic maintenance measures during the life cycle of the pipelines. The case study involves the calculation of the failure probability due to equipment impact, the calculation of the failure probability due to corrosion, and the estimation the re-inspection interval for domestic natural gas transmission pipelines.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.40 no.9
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• pp.821-826
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• 2016

The leak before break (LBB) concept is used in pipe line design for nuclear power plants. For application of the LBB concept, leak rates through cracks should be evaluated accurately. Usually leak late analyses are performed for through-thickness cracks with constant cross-sectional area. However, the cross-sectional area at the inner pipe surface of a crack can be different from that at the outer surface. In this paper, leak rate analyses are performed for the cracks with linearly-varying cross-sectional areas. The effect of varying the cross-sectional area on leak rates was examined. Leak rates were also evaluated for cracks in bi-material pipes. Finally, the effects of crack surface morphology parameters on leak rates were examined.

• Journal of the Korean Society for Nondestructive Testing
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• v.28 no.4
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• pp.323-330
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• 2008

High cycle bending fatigue of socket welded small bore pipe was characterized, and also the fatigue crack initiation of small bore pipe was monitored in situ by the acoustic emission (AE) technique. The STS 316L stainless steel specimens were prepared by gas tungsten arc welding (GTAW) process having the artificial defect (i.e., lack of penetration) and defect free at the root. The fatigue failure was occurred at the loc for high stress and root for relatively low stress. The crack initiation cycles ($N_i$) was defined to the abrupt increase in AE counts during the fatigue test, and then the cracks were observed by the radiographic test and electron microscope before and after the fatigue crack initiation cycles. The socket welded pipe damaged by bending fatigue was studied regarding the welding defect, failure mode, and crack initiation cycles for the diagnosis and monitoring.