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임혁순(Hyuk-Soon LIM),박영섭(Young-Sheop PARK),이광한(Kwang-Han LEE),이석호(Seok-Ho LEE),정대율(Dae-Yul CHUNG) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.
SLURP 모형을 이용한 광역적 수문분석 - 소양강댐 유역을 대상으로 -
임혁진 ( Lim Hyuk Jin ),권형중 ( Kwon Hyung Joong ),장철희 ( Jang Cheol Hee ),김성준 ( Kim Seong Joon ) 한국농공학회 2003 한국농공학회 학술대회초록집 Vol.2003 No.-
This study is to test the applicability of SLURP (Semi-distributed Land Use-based runoff Process) model that is a semi-distributed, continuous hydrologic model developed by Kite (1997). The Soyanggang-dam watershed (2,694km<sup>2</sup>) was selected. The DEM, land-cover map, monthly NDVI from NOAA/ A VHRR and daily meteorological data of 2001 were prepared. By using the parameter optimization technique, SCE-UA (Shuffled Complex Evolution-University of Arizona), the model was calibrated and the Nash-Sutcliffe efficiency was 0.73.
임혁순(Hyuk-Soon Lim),지문구(Moon-Goo Chi),김순용(Soon-Yong Kim) 대한전기학회 2010 대한전기학회 학술대회 논문집 Vol.2010 No.7
원자력발전소 터빈발전기에서 생산된 전력은 송전망으로 공급되며 발전소 운전에 필요한 기기에 신뢰성 있는 직류 및 교류가 공급되도록 설계되어 있다. 최근 원자력발전소 비안전 등급 충전기출력차단기의 비정상적인 트립이 발생하였는바 근본원인 분석을 위해 전자계 해석을 통한 충전기 차단기 동작 원리 분석, 부하로부터 트립 유발가능성 분석, 충전기/인버터의 결함 가능성 분석 및 성능기준을 설정하고 개선 방안을 제시하여 직류계통의 신뢰성 향상에 기여하고자 한다.
임혁순(Hyuk-Soon Lim),이은찬(Eun-Chan Lee),이근성(Keun-Sung Lee),황석원(Seok-Won Hwang),성기열(Ki-Yeoul Seong) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
Recently, nuclear power plant companies have been extending the turbine valve test interval to reduce the potential of the reactor trip accompanied with a turbine valve test and to improve the NPP's economy through the reduction of unexpected plant trip or decreased operation. In these regards, the extension of the test interval for turbine valves was reviewed in detail. The effect on the destructive overspeed probability due to the test interval change of turbine valves is evaluated by Fault Tree Analysis(FTA) method. Even though the test interval of turbine valves is changed from 1 month to 3 months, the analysis result shows that the reliability of turbine over speed protection system meets acceptance criteria of 1.0E-4/yr. This result will be used as the technical basis on the extension of the test interval for turbine valves. In this paper, the propriety of the turbine valve test interval extension is explained through the review on the turbine valve test interval status of turbine overspeed protection system, the analysis on the annual turbine missile frequency and the probability evaluation of the destructive overspeed due to the test interval extension.
신형경수로의 증기발생기 전열관 재질 Inconel-690 적용
임혁순(Hyuk-Soon LIM),정대율(Dae-Yul CHUNG),변성철(Sung-chul BYUN),이광한(Kwang-Han LEE) 대한기계학회 2003 대한기계학회 춘추학술대회 Vol.2003 No.4
Most of the operating pressurized water reactors (PWRs) has chosen Inconel 600 as steam generator tubing. The long-term operation of steam generators showed that the use of this material induced localized corrosion damages. The current trend is using Inconel 690 as a tube material for the replacement steam generators. Based on the current trend, we have chosen Inconel 690 for the Advanced Power Reactor 1400 (APR1400) steam generator tube material. In this paper, we examined the technical consideration in this modification:the effect of chemical composition, thermal conductivity, corrosion resistance and wear characteristics
원전 케이블 화재 열속평가 및 열화 진단방법에 관한 연구
임혁순 ( Hyuk Soon Lim ),김두현 ( Doo Hyun Kim ) 한국안전학회(구 한국산업안전학회) 2011 한국안전학회지 Vol.26 No.2
The fire event occurred in fire proof zone often causes serious electrical problems such as shorts, ground faults, or open circuits in nuclear power plants. These would be directed to the loss of safe shutdown capabilities performed by safety related systems and equipments The fire event can treat the basic design principle that safety systems should keep their functions with redundancy and independency. In case of a multi-core cable fire, operators can not perform their mission properly and can misjudge the situation because of spurious operation, wrong indication or instrument. These would deteriorate the plant capabilities of safety shutdown and make disastrous conditions. In this paper, the characteristic of cable fire is investigated and the heat-flux evaluation for cable fire is studied. Moreover, a diagnostic methodology for degraded cable in nuclear power plants is presented.