• 대한기계학회논문집A
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• 제38권9호
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• pp.1043-1048
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• 2014

체결부품의 사이즈가 작아질수록 실제 접합부의 면적이 줄어들기 때문에 체결력은 감소한다. 이러한 체결부품의 체결력을 결정하는 요소는 소재(Material), 구조(Geometry), 마찰(Friction)이 있다. 본 연구에서는 체결부품의 사이즈가 줄어들면서 체결력을 향상시킬 수 있는 방법 중의 하나인 소재 변경에 대하여 연구하였다. SWCH18A 와 SUS XM7 을 적용하여 초소형 나사를 제작하였으며, 3 차원 치수 측정을 통하여 피치정밀도와 두께정밀도를 측정하였다. 비커스 경도 측정을 통하여 나사가 외부의 힘에 의해 변형에 대한 저항력을 분석하였다. 또한 파단토크 시험과 SEM 을 이용한 파단면 분석을 통해 파단특성을 분석한다.

• 대한기계학회논문집A
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• 제35권6호
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• pp.651-659
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• 2011

최근 열출력이 향상된 신규 원자력발전소의 개발이 증가하고 있으며 배관계에 가해지는 모멘트 및 하중의 크기도 증가하는 경향이므로 배관의 파단전누설(LBB) 적용조건 여유도가 작아질 수 있다. 본 논문에서는 이러한 배관에서 LBB 적용조건을 만족시키기 위한 추가적인 여유도 확보의 한 방법으로써 균열의 비선형과 재료물성치를 고려하는 방법을 제시하였다. 균열 및 재료의 비선형을 고려하기 위하여 유한요소해석과 보(beam) 이론을 병용하였다. 원자력 배관을 모델로 하여 본 논문에서 제안한 방법으로 LBB 균열안정성 해석을 수행하였으며, LBB 여유도가 낮은 위치에서 균열 및 재료 비선형을 고려함으로 써 추가적인 LBB 여유도를 확보할 수 있음을 확인하였다.

• 에너지공학
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• 제16권3호
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• pp.103-112
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• 2007

국내 1970년대에 설계 및 건설된 원자력발전소에 대해 침수분석을 수행한 결과 기기냉각수펌프 및 열교환기 건물, 주/보조건물, 중간건물 주증기 헤더 격실, 중간건물 주급수관 지역 및 하부층 등이 침수사고에 매우 취약하며 발전소 안전정지능력을 저해할 정도로 침수 영향이 심각한 것으로 판명되었다. 이들 지역에서의 침수원은 주급수관 파단이다. 현재 원자력발전소 내환경기기검증에서 주급수관 파단 방출량 계산은 수계산(Hand calculation)방법으로 Henry-Fauske 임계유량 모델 사용하고 있다. 이 방법은 배관파단 위치에서의 차압으로 계산되며, 실제 원자력발전소의 각종 제어로직에 의한 격리신호를 반영하지 못하므로 지나치게 보수적으로 파단 방출유량이 계산된다. 이러한 문제점을 개선하기 위해 원자력발전소 열수력계통 해석 전산코드인 RETRAN을 사용하여 원자력발전소 일/이차측 계통과 제어로직을 모사하고, 주급수관 파단 방출량 분석을 위한 입력가정과 해석방법을 개발하였다. 침수위 분석은 웨스팅하우스형 원자력발전소 격납건물 외부 하부격실에 대해 적용하였다. 전산코드 해석에서 각종 제어계통과 로직을 고려하였으며, 가장 제한적 사고조건을 계산하기 위해 노심출력, 파단형태, 면적, 위치 등의 조합으로 구성된 18개 사고 사례를 분석하였다. 그 결과 가장 제한적 사례 분석에서는 기존 수계산 분석에서보다 파단 방출유량이 크게 줄었고, 하부격실의 침수위도 상당히 낮아졌다.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2009년도 추계학술대회
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• pp.461-464
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• 2009

대규모 DC 전력 시스템에서는 회로차단기(circuit break)와 계전기(relay)로 대표되는 기존의 전자기적 회로차단기가 현재 산업 전 분야에 널리 사용 되고 있으나, 최근에는 고 신뢰성, 원격제어능력, 과부하와 단락전류 보호, 적은 열손실(dissipation) 등의 장점을 가지고 있는 원격전력제어기(Remote Solid State Power controller)를 MOSFET 반도체 스위칭 소자를 이용하여 개발하고 있는 추세이며 고품질을 요구하는 시스템에서는 필수적인 부품이 되어가고 있다. 본 논문에서는 회로차단기와 계전기의 기능을 통합한 원격전력제어장치의 $I^2T$ 커브에 대한 이론 분석과 전체 회로 동작에 대한 시뮬레이션 분석을 수행한다.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.1029-1040
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• 2021

For the structural integrity evaluation of pressurized water reactor (PWR) steam generator (SG) tubes subjected to transient hydraulic loading, determination of the tube-to-tube gap velocity and static pressure distributions along the tubes is prerequisite. This paper addresses both computational fluid dynamics (CFD) and analytical approaches for predicting the tube-to-tube gap velocity and static pressure distributions during blowdown following a feedwater line break (FWLB) accident at a PWR SG. First of all, a comparative study on CFD calculations of the transient velocity and pressure distributions in the SG secondary sides for two different models having 30 or no tubes is performed. The result shows that the velocities of sub-cooled water flowing between any adjacent two tubes of a tubed SG model during blowdown can be roughly estimated by applying the specified SG secondary side porosity to those of the no-tubed SG model. Secondly, simplified analytical approximate solutions for the steady two-dimensional SG secondary flow velocity and pressure distributions under a given discharge flowrate are derived using a line sink model. The simplified analytical solutions are validated by comparing them to the CFD calculations.

• 한국전산유체공학회지
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• 제20권2호
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• pp.52-60
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• 2015

The objective of this research lies in the effect of installation parameters influencing on the wind proof performance of the coastal forest for damage prevention. The dissipation ratio of incident wind power is developed as an assessment index to make a lumped parameter study possible. From the real field data of East, West, and South Sea bounded on the Korean peninsula, single and double storied forests were modeled in three-dimensional shape with computer aided design, and so was done the artificial structures such as wind break, sand accumulating fence, and sand dune, etc With a commercial code ANSYS-CFX, the computational result from the comparison of dissipation ratio between single and double storied forest shows the effect of composition, and also the installation effect is investigated for artificial structures with optimal dimension of distance.

• 대한기계학회논문집
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• 제19권4호
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• pp.1051-1061
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• 1995

In order perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain (.sigma. - .epsilon.) curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to develop two methods for J-R curve prediction. In the first method, elastic-plastic finite element analyses for a series of crack length / specimen width ratio were performed. Accordingly the load versus load line displacement (P .delta.) curve corresponding to the fracture strain is obtained and the J-R curve based on the generalized locus method is obtained. In the second method, the correlation between .sigma.-.epsilon. curves and J-R curves was statistically analyzed and an empirical equation to predict the J-R curve from the .sigma.-.epsilon. test result is proposed. A good correlation between the predicted results based on the proposed methods and the experimental ones is obtained.

• 한국전기전자재료학회논문지
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• 제20권10호
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• pp.839-845
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• 2007

In this paper, a polishing pad has been analyzed in detail, to understand surface phenomena of polishing process. The polishing pad plays a key role in polishing process and is one of the important layer in polishing process, because it is a reaction layer of polishing[1]. Pad surface physical property is also ruled by pad profile. The profile and roughness of pad is controlled by different types of conditioning tool. Conditioning tool add mechanical force to pad, and make some roughness and profile. Formed pad surface will affect on polishing performance such as RR (Removal Rate) and uniformity in CMP Pad surface condition is changed by conditioning tool and dummy run and is stable at final. And this research, we want to reduce break-in and dummy polishing process by analysis of pad surface and artificial machining to make stable pad surface. The surface treatment or machining enables to control the surface of polishing pad. Therefore, this research intends to verify the effect of the buffing process on pad surface through analysis of the removal rate, friction force and temperature. In this research, urethane polishing pad which is named IC pad(Nitta-Haas Inc.) and has micro pore structure, is studied because, this type of pad is most conventional type.

• Nuclear Engineering and Technology
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• 제47권4호
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• pp.434-442
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• 2015

The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant system, the actuation of the PRHR will enhance the cooldown of the primary coolant system. There is a risk of power excursion during the cooldown of the primary coolant system. Therefore, it is necessary to analyze the thermal hydraulic behavior of the reactor coolant system (RCS) at this condition. The advanced passive PWR model, including major components in the RCS, is built by SCDAP/RELAP5 code. The thermal hydraulic behavior of the core is studied for two typical accident sequences with PRHR actuation to investigate the core cooling capability with conservative assumptions, a main steam line break (MSLB) event and inadvertent opening of a steam generator (SG) safety valve event. The results show that the core is ultimately shut down by the boric acid solution delivered by Core Makeup Tank (CMT) injections. The effects of CMT boric acid concentration and the activation delay time on accident consequences are analyzed for MSLB, which shows that there is no consequential damage to the fuel or reactor coolant system in the selected conditions.

• 에너지공학
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• 제12권2호
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• pp.101-108
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• 2003

The purpose of this study is to develop an entrainment model of the Pressurized Water Reactor (PWR) U-tube Steam Generator (SG) for Main Steam Line Break (MSLB) analyses. Generally, the temperature of the inside containment vessel at MSLB is decreased by introducing the liquid entrainment effect. This effect makes a profit on the aspect of integrity evaluation for Equipment Environmental Qualification (EEQ) in the containment. However, the target plant, Kori unit 1 does not have the entrainment data. Therefore, this study has been performed. RETRAN-3D and LOFTRAN computer programs are used for the model development. There are several parameters that are used for the initial benchmark, such as Combustion Engineerings (CE) experimental data and the RETRAN-3D model which describes the test leg. A sensitivity study is then performed with this model in which the model parameters are varied until the calculated results provide reasonable agreement with the measured results for the entire test set. Finally, a multiplication factor has been obtained from the 95/95 values of the calculated (best-estimate) quality data relative to the measured quality data. With this new methodology, an additional temperature margin of about 40$^{\circ}C$ can be obtained. So, the new methodology is found to have an explicit advantage to EQ analyses.