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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.
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.
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.
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.
전기안전분야 : 원전 노출 화재시 케이블 기능상실 온도에 관한 연구
김두현 ( Doo Hyun Kim ),임혁순 ( Hyuk Soon Lim ) 한국안전학회(구 한국산업안전학회) 2011 한국안전학회지 Vol.26 No.5
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 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 cables of the representative nuclear power plant in korea is selected and the cable functional failure temperature by exposed fire using Cable Response to Live Fire(CAROLFIRE) is studied. It is expected that the results are very useful to know the cable failure temperature by exposed fire. We confirmed the safety and integrity of the cable by exposed fire and those results will use the based data of cable exposed fire characteristics.
이근성(Keun-Sung LEE),임혁순(Hyuk-Soon LIM),이은찬(Eun-Chan LEE) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
Power uprate is the process of increasing the maximum power level at which a commercial nuclear power plant may operate. Power uprate applications(113 units) for NPPs(Nuclear Power Plants) were recently approved in the United States. Utilities have been using power uprates since the 1970s as a way of increasing the power output of their nuclear plants. To increase the power output of a reactor, typically more highly enriched uranium fuel and/or more fresh fuel is used. This enables the reactor to produce more thermal energy and therefore more steam, driving a turbine generator to produce electricity. In this paper, the propriety of power uprate is explained through the review on the power uprate method and the changes of the physical parameters due to power uprate. The analysis results showed that the CDF(Core Damage Frequency) and LERF(Large Early Release Frequency) are affected in the current probabilistic safety assessment (PSA) model.