• Proceedings of the KSME Conference
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• 2001.11a
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• pp.16-21
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• 2001

The PTS reference temperature of reactor pressure vessel for one of the Korean NPPs has been predicted to exceed the screening criteria before it reaches it's design life. To cope with this issue, a plant-specific PTS analysis had been performed in accordance with the Regulatory Guide 1.154 in 1999. As a result of that analysis, it was found that current methodology of RG. 1.154 was very conservative. The objective of this study is to examine the effects of changing various input parameters and to determine the amount of conservatism of the current PTS analysis method. To do this, based on the past PTS analysis experience, parametric study were performed for various models using modified VISA-II code. This paper discusses the analysis results and recommendations to reduce the conservatism of current analysis method.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.15 no.2
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• pp.40-49
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• 2019

In this paper, failure probabilities of the OPR1000 reactor vessel under pressurized thermal shock (PTS) were estimated using the probabilistic fracture mechanics code, R-PIE. Input variables of initial crack distribution, crack size, copper contents, and upper shelf toughness were selected for the sensitivity analyses. A wide range of the input data were considered. Through-wall cracking frequencies determined by the product of the vessel failure probability and the corresponding occurrence frequency of the transient were also compared to the acceptance criterion. The results showed that transient history had the most significant impact on the vessel failure probability. Moreover, conservative assumptions resulted in extremely high through-wall cracking frequencies.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.6 no.2
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• pp.42-46
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• 2010

The evaluation method for the failure frequency of reactor vessel under pressurized thermal shock(PTS) is developed using probabilistic fracture mechanics. The probabilistic reactor integrity evaluation code, named R-PIE code, is developed. The validity and uncertainty of the R-PIE code is investigated. The reactor failure frequencies under PTS for Kori-1 nuclear power plant and other type of domestic nuclear power plants are evaluated. The reference PTS temperature for domestic nuclear power plants is obtained for the rule making against PTS failure.

• Composites Research
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• v.18 no.3
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• pp.38-46
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• 2005

In order to characterize the outstanding performance of three-dimensional (3D) composites, the low velocity impact test has been carried out. 3D fiber structures have been achieved by using the automated tape placement (ATP) process and a stitching method. Materials for the ATP and the stitching process were carbon/epoxy prepreg tapes and Kevlar fibers, respectively. Two-dimensional composites with the same stacking sequence as 3D counterparts have also been fabricated for the comparison of damage tolerance. For the assessment of damage after the impact loading, specimens were subjected to C-Scan nondestructive inspection. Compression after impact (CAI) tests were conducted to evaluate residual compressive strength. The damage area of 3D composites was greatly reduced $(30-40\%)$ compared with that of 2D composites. Although the CAI strength did not show drastic improvement for 3D composites, the ratio of retained strength was $5-10\%$ higher than 2D samples. The effect of stitching on the impact performance was negligible above the energy level of 35 Joules.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.359-364
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• 1996

'93.4월에 고리원자력 4호기 운전중(원자로 출력 100%, 발전기 출력 975MWe) 주증기 차단밸브 (MSIV)의 닫힘으로 인해 발전소가 정지되었다. 밸브분해 점검결과 밸브스템이 Back Seat Ring 조립부위 Notch 부위에서 Steam Flow와 평행한 방향으로 절단되어, 밸브스템의 손상원인을 규명하기 위한 본 연구에서는 피로해석절차도에 따라 S-N 곡선에 근거하여 피로해석을 수행하였다. 피로해석결과 밸브스템의 초기균열 생성원인은 Stem Notch 부위의 제작결함과 발전소 정지시 밸브를 급속히 닫을 때 작용하는 충격하중등에 의해 발생된 것으로 추정되며 인장평균응력과 관내 유체의 진동하중의 변동응력이 조합하여 피로균열을 가속시켜 파손을 일으킨 것으로 사교된다.

• Proceedings of the KIEE Conference
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• 2015.07a
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• pp.687-688
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• 2015

기존의 Porcelain Bushing은 기계적 성능이 약하여 작은 충격에도 손상이나 파손 등이 발생되며 오손에 의한 전기적 성능의 저하로 오염이 심한지역에서의 사용이 제한되며 정기적으로 세정등 유지보수가 필요하다. 이러한 문제점을 보완하기 위해 절연성능 및 내 오손 특성이 우수한 Composite Bushing으로 바뀌고 있는 추세이다. 당사에서는 최근에 170kV GIS용 Composite Bushing 인증을 완료하였으며 본 논문에서는 362kV급 GIS용 Composite Bushing에 대한 개발 내용을 기술하였다.

• Journal of the KSME
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• v.30 no.2
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• pp.107-114
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• 1990

(1) Cr-Mo-V 합금강 로우터재료는 사용도중 템퍼 취화된다. 템퍼취화된 소재는 취성제거처리 혹 은 재열처리를 하여 취성을 감소시킬 수 있다. (2) 축의 신뢰도를 파괴역학 원리를 적용하여 계산하였으며 템퍼 취화된 소재는 파손 위험성이 있으나 열처리 된 소재는 취성파괴 및 고 사이클 하중에 의한 피로균열 성장에 대해서 안전성 이 충분하다는 결론을 얻을 수 있다. (3) 샬피 V-노치 충격치 (CVN)와 파괴인성치(K$_{tc}$ )의 관계식을 취성재료에도 적용할 수 있 는가의 여부에 대해서는 많은 조사가 필요하다. (4) 취성소재의 피로균열 개시값$\Delta$ $K_{th}$을 알고 있으면 취송소재로 제조된 구조물의 파괴역학적인 해석을 하는데 도움을 줄 수 있다.

• Proceedings of the Korean Society of Fisheries Technology Conference
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• 2003.05a
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• pp.61-63
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• 2003

열경화성 복합재료는 고가이며, 성형시간이 길고, 파손시 수리가 불리한 점이 있으므로 열경화성 복합재료의 특징인 경량, 고강도와 고강성의 특성을 가지고 있으면서 성형시간이 짧고, 저가이며, 재활용과 수리 또한 유리한 잇점이 있는 열가소성 복합재료가 지난 10년동안 열경화성 복합재료를 대신하여 서서히 대체되고 있으나, 열가소성 복합재료는 환경적인 요인, 즉 수분과 온도에 대해 매우 민감한 것으로 알려져 있다. (중략)

• Journal of the korean Society of Automotive Engineers
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• v.12 no.2
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• pp.11-15
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• 1990

고무재료는 강재에 비해 큰 탄성변형을 할 수 있고 충격 흡수능력이 뛰어나므로 자동차에서도 진동문제 및 승차감을 향상시키기 위하여 엔진 마운트, suspension bushing등을 비롯한 여러 곳에 사용되고 있다. 여기에 이용되는 고무재의 요구조건은 1) 피로수명이 충분히 길것, 2) 열 및 산화에 강할 것, 3) 소음이 없을 것 등이다. 본 고에서는 1)번의 요구조건을 기준으로 고무재의 기본적인 역학적 특성 및 해석방법을 소개하고자 한다.

• The Journal of the Acoustical Society of Korea
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• v.14 no.4
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• pp.12-20
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• 1995

This paper describes principles and experimental results in conjunction with examining the possibility of the detection of effects from a cylindrical objects. Cylindrical objects have its own resonance frequency. The frequency varies according to the diameter, length etc. And acoustic sound, whose frequency and the harmonic components corresponding to resonance frequency, is radiated from the object. When an object have defect in itself, the radiated acoustic sound is different from normal one. So we can detect its defect by analysing frequency components of acoustic sound. We proved that detection of defective objects by acoustic signal analysis is possible automatically. Also the result can be applied to other kinds of objects.