• Journal of Mechanical Science and Technology
• /
• 제19권11호
• /
• pp.1988-1997
• /
• 2005

This study is concerned with structural integrity evaluations for the interference-fit flywheels in reactor coolant pumps (RCPs) of nuclear power plants. Stresses in the flywheel due to the shrinkage loads and centrifugal loads at the RCP normal operation speed, design overspeed and joint-release speed are obtained using the finite element method (FEM), where release of the deformation-controlled stresses as a result of structural interactions during rotation is considered. Fracture mechanics evaluations for a series of cracks assumed to exist in the flywheel are conducted, considering ductile (fatigue) and non-ductile fracture, and stress intensity factors are obtained for the cracks using the finite element alternating method (FEAM). From analysis results, it is found that fatigue crack growth rates calculated are negligible for smaller cracks. Meanwhile, the material resistance to non-ductile fracture in terms of the critical stress intensity factor (K$_{IC}$) and the nil-ductility transition reference temperature (RT$_{NDT}$) are governing factors for larger cracks.

• 한국정보전자통신기술학회논문지
• /
• 제14권6호
• /
• pp.452-460
• /
• 2021

전 세계적으로 전기차 시장이 확대됨에 따라 성능 및 안전성의 문제를 보완한 친환경적인 전기차가 계속 출시되고 시장이 더욱 커지고 있다. 하지만 전기차의 경우 충전의 불편함, 감전과 같은 안전 문제, 여러 전장부품들의 연동으로 인한 EMI(Electromagnetic interference) 문제는 전기차에서 해결해야 하는 문제이다. 무선전력전송 기술을 이용하면 전기차 충전에 대한 불편함 해소와 고전류, 고전압을 직접 다루지 않아 안전성의 문제를 해결할 수 있으나 EMI 저감을 위한 설계가 이루어지지 않는다면 오작동을 일으켜 더 큰 문제를 일으킬 수 있다. 본 논문은 전기차 무선전력전송 핵심 전장 부품인 무선충전컨트롤모듈에서 발생할 수 있는 EMI를 저감시키기 위한 전원무결성과 신호무결성을 갖는 전기차 무선전력전송 무선충전컨트롤모듈 EMI 저감 설계하였다. 전원부분에서 발생할 수 있는 공진, 임피던스 등의 문제와 신호 부분에서 발생할 수 있는 고속통신간의 신호왜곡의 문제를 시뮬레이션을 통해 EMI 저감 설계하였다.따라서 전원무결성과 신호무결성을 갖는 EMI 저감 설계를 통해 전기차 무선전력전송 무선충전컨트롤모듈 800 MHz ~ 1 GHz 대역과 1.5 GHz에서 각각 10 dBu V/m, 15 dBu V/m이 저감되는 것을 확인하였다.

• 방사성폐기물학회지
• /
• 제3권3호
• /
• pp.231-236
• /
• 2005

원전에서 발생하는 건조폐수지를 함유한 고건전성용기(HIC, high integrity container)를 운반하기 위한 HIC 운반용기는 내용물의 높은 방사능으로 인하여 원자력법 및 IAEA의 안전수송규정의 B형 운반용기의 요건을 따라야 하고 정상운반 및 운반사고조건에 대하여 구조적 건전성을 유지하여야 한다. 운반용기는 최대손상을 야기하는 위치에서 단단한 바닥면 위로 9 m 높이에서의 자유낙하충격 및 연강봉 위로의 1 m 높이에서의 낙하충격을 견디어야 한다. HIC 운반용기의 개념설계를 위하여 9 m 자유낙하 및 1 m 파열조건에 대하여 ABAQUS 전산코드를 이용한 3차원동적 구조해석을 수행하고 건전성을 평가하였다.

• 대한전기학회:학술대회논문집
• /
• 대한전기학회 2005년도 추계학술대회 논문집 전기설비전문위원
• /
• pp.73-75
• /
• 2005

A number of the power cables arc installed in the containment of the nuclear power plant. According to the IEEE Standard 835, the calculation of the temperature rise shows the operation possibility of power cables in the containment. In this paper, we expect the integrity of the power cables by using the calculation of the temperature rise and the development of the lifetime extension of the cables.

• 대한기계학회논문집A
• /
• 제27권6호
• /
• pp.930-937
• /
• 2003

The extension of design life among power plants is increasingly becoming a world-wide trend. Kori #1 unit in Korea is operating two cycle. It has two man-ways for tube inspection in a steam generator which is one of the important components in a nuclear power plant. Especially, stud bolts fur man-way cover have damaged by disassembly and assembly several times and degradation for bolt materials for long term operation. It should be evaluated and compared by ASME Code criteria for integrity evaluation. Integrity evaluation criteria which has been made by the manufacturer is not applied on the stud bolts of nuclear pressure vessels directly because it is controlled by the yield stress of ASME Code. It can apply evaluation criteria through FEM analysis to damaged female threads and to evaluated safety fer helical-coil method which is used according to Code Case-N-496-1. From analysis results, we found .that it is the same results between stress intensity which got from FEM analysis on damaged female threads over 10％ by manufacture integrity criteria and 2／3 yield strength criteria on ASME Code. It was also confirmed that the helical-coil repair method would be safe.

• Nuclear Engineering and Technology
• /
• 제44권7호
• /
• pp.817-824
• /
• 2012

The most important component of a nuclear power plant is its nuclear reactor. Studies on the integrity of reactors have become an important part regarding the safety of a nuclear power plant. The US Nuclear Regulatory Commission Regulatory Guide (NRC RG) 1.20 presents a Comprehensive Vibration Assessment Program (CVAP) to be used to verify the structural integrity of the Reactor Vessel Internals (RVI) for flow-induced vibration prior to commercial operation. However, there are few published studies related to the RVI CVAP. We classified the Advanced Power Reactor 1400 (APR1400) RVI CVAP as a non-prototype category-2 reactor as part of an independent validation of its design. The aim of this paper is to present the results of structural response analyses of the Upper Guide Structure (UGS) assembly of the APR1400 reactor. These results show that the UGS and the Inner Barrel Assembly (IBA) meet the specified integrity levels of the design acceptance criteria. The vibration and stress analysis results in this paper will be used as basic information to select measurement locations of the vibration and stress for the APR1400 RVI CVAP.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2004년도 추계학술대회
• /
• pp.166-171
• /
• 2004

Since early 1950's fracture mechanics has brought significant impact on structural integrity assessment in a wide range of industries such as power, transportation, civil and petrochemical industries, especially in nuclear power plant industries. For the last two decades, significant efforts have been devoted in developing defect assessment procedures, from which various fitness-for-purpose or fitness-for-service codes have been developed. From another aspect, recent advances in IT (Information Technologies) bring rapid changes in various engineering fields. IT enables people to share information through network and thus provides concurrent working environment without limitations of working places. For this reason, a network system based on internet or intranet bas been appeared in various fields of business. Evaluating the integrity of structures is one of the most critical issues in nuclear industry. In order to evaluate the integrity of structures, a complicated and collaborative procedure is required including regular in-service inspection, fracture mechanics analysis, etc. And thus, experts in different fields have to cooperate to resolve the integrity problem. In this paper, an internet-based cooperative system for integrity evaluation system which adapts IT into a structural integrity evaluation procedure for reactor pressure vessel is introduced. The proposed system uses Virtual Reality (VR) technique, Virtual Network Computing (VNC) and agent programs. This system is able to support 3-dimensional virtual reality environment and to provide experts to cooperate by accessing related data through internet.

• 대한전자공학회:학술대회논문집
• /
• 대한전자공학회 2008년도 하계종합학술대회
• /
• pp.1195-1196
• /
• 2008

It is difficult to solve PCB(Printed Circuit Board) Noise problem. Because Electronic circuit system operates very high frequency. Resonance analysis of PCB layout by PI(Power Integrity) Simulation method visualizes distribution of Switching noise between VDD and GND. By using de-cap, we reduce impedance and solve the EMI problems.

• International Journal of Advanced Culture Technology
• /
• 제8권2호
• /
• pp.226-230
• /
• 2020

The nation is currently deeply dissatisfied with the corruption of power. The incumbent government promised to create a fair society without fouls and privileges. However, the public is deeply distrusted by the prosecution's investigation of the justice minister. Korean society has very low national integrity due to corruption in public offices. In the past, corruption in public offices was mostly corruption in the form of livelihood, but it has now turned into corruption in power. This paper looks into the concept and theory of corruption in public office and tries to find alternatives.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
• /
• pp.345-346
• /
• 2018