http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
제주 시설온실 냉난방을 위한 발전소 온배수 활용 열펌프 시스템 구축 및 냉방성능 평가
이연건,허재혁,이동원,현명택 한국에너지학회 2018 에너지공학 Vol.27 No.4
한국중부발전 제주화력본부에서 방류되는 온배수로부터 열원을 회수하여 약 3 km의 원거리에 위치하고 있는신촌백합영농조합법인의 시설온실에 냉온수를 공급하기 위한 300 RT 용량의 열펌프 시스템을 구축하였다. 원거리 시설로 온배수열을 공급하기 위한 최적화 방안을 도출하였고, 수송관로의 온도와 누수여부를 모니터링하기위한 설비들이 설치되었다. 본 논문에서는 제주 시설온실 냉난방을 위한 발전소 온배수 활용 열펌프 시스템의구성과 주요기기에 대해 기술하였다. 2018년 하절기에 열펌프 시스템의 냉방성능을 평가하기 위한 실증운전을수행하였다. 냉방운전 시 열펌프 시스템의 주요 위치에서 측정된 유체의 온도와 유량, 그리고 냉방 성능계수를분석하여, 구축된 열펌프 시스템의 안정성과 냉방성능을 검증하였다.
SBLOCA and LOFW Experiments in a Scaled-Down IET Facility of REX-10 Reactor
이연건,박일웅,박군철 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.3
This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOCA) and the loss-offeedwater accident (LOFW) in a scaled integral test facility of REX-10. REX-10 is a small integral-type PWR in which the coolant flow is driven by natural circulation, and the RCS is pressurized by the steam-gas pressurizer. The postulated accidents of REX-10 include the system depressurization initiated by the break of a nitrogen injection line connected to the steam-gas pressurizer and the complete loss of normal feedwater flow by the malfunction of control systems. The integral effect tests on SBLOCA and LOFW are conducted at the REX-10 Test Facility (RTF), a full-height full-pressure facility with reduced power by 1/50. The SBLOCA experiment is initiated by opening a flow passage out of the pressurizer vessel,and the LOFW experiment begins with the termination of the feedwater supply into the helical-coil steam generator. The experimental results reveal that the RTF can assure sufficient cooldown capability with the simulated PRHRS flow during these DBAs. In particular, the RTF exhibits faster pressurization during the LOFW test when employing the steam-gas pressurizer than the steam pressurizer. This experimental study can provide unique data to validate the thermal-hydraulic analysis code for REX-10.
TAPINS: A Thermal-Hydraulics System Code for Transient Analysis of A Fully-Passive Integral PWR
이연건,박군철 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.4
REX-10 is a fully-passive small modular reactor in which the coolant flow is driven by natural circulation, the RCS is pressurized by a steam-gas pressurizer, and the decay heat is removed by the PRHRS. To confirm design decisions and analyze the transient responses of an integral PWR such as REX-10, a thermal-hydraulic system code named TAPINS (Thermal-hydraulic Analysis Program for INtegral reactor System) is developed in this study. Based on a one-dimensional four-equation drift-flux model, TAPINS incorporates mathematical models for the core, the helical-coil steam generator, and the steam-gas pressurizer. The system of difference equations derived from the semi-implicit finite-difference scheme is numerically solved by the Newton Block Gauss Seidel (NBGS) method. TAPINS is characterized by applicability to transients with non-equilibrium effects, better prediction of the transient behavior of a pressurizer containing non-condensable gas, and code assessment by using the experimental data from the autonomous integral effect tests in the RTF (REX-10 Test Facility). Details on the hydrodynamic models as well as a part of validation results that reveal the features of TAPINS are presented in this paper.
환형채널 내 저압 미포화비등 유동장의 국소 이상유동 변수 측정
이연건(Yeon-Gun Lee),유지웅(Ji-Woong Yoo),김신(Sin Kim) 대한기계학회 2018 大韓機械學會論文集B Vol.42 No.12
대기압 주변 저압조건에서 미포화비등 유동장 내 국소 기포인자를 측정하기 위한 실험 연구를 수행하였다. 시험부는 유효 가열길이 2 m의 수직 환형채널이며, 기포변수의 측정에 광섬유센서를 적용하였다. 네 군데의 높이에서 국소 기포율, 평균 기포속도, 계면면적밀도, Sauter mean diameter를 측정하였으며, 광섬유센서의 측정 팁을 이송함으로써 각 높이에서의 반경방향 단면 분포를 획득하였다. 실험에서 유동 조건은 열속 370 kW/m², 질량속 430~680 kg/m²s, 입구 과냉각도 12~18 K, 그리고 압력 114~152kPa의 범위로 조절하였다. 국소 기포인자의 다차원 분포 측정 결과는 전산유체역학 코드의 벽면 비등모델 검증에 유용하게 활용될 수 있다. In this study, an experimental investigation is performed to measure the local bubble parameters in steam-water subcooled boiling flow under atmospheric pressure conditions. The test section is a vertical concentric annulus with an effective height of 2 m, and optical fiber probes are used to measure various local bubble parameters during boiling of the subcooled flow. The local void fraction, mean bubble velocity, interfacial area density, and Sauter mean diameter are measured at four elevations, and their radial profiles are obtained by traversing the tip of optical probes. In the experiments, the flow conditions were set for a heat flux of 370 kW/m², a mass flux of 430~680 kg/m²s, and an inlet subcooling of 12~18 K at pressures ranging from 114 to 152 kPa.
새로운 응축열전달계수 상관식이 적용된 MARS-KS를 활용한 원자로건물 피동냉각계통 열제거 성능의 수치적 연구
장영준,이연건,김신,임상규 한국에너지학회 2018 에너지공학 Vol.27 No.4
The passive containment cooling system (PCCS) has been designed to remove the released decayheat during the accident by means of the condensation heat transfer phenomenon to guarantee the safetyof the nuclear power plant. The heat removal performance of the PCCS is mainly governed by the condensationheat transfer of the steam-air mixture. In this study, the heat removal performance of the PCCSwas evaluated by using the MARS-KS code with a new empirical correlation for steam condensation inthe presence of a noncondensable gas. A new empirical correlation implemented into the MARS-KS codewas developed as a function of parameters that affect the condensation heat transfer coefficient, such asthe pressure, the wall subcooling, the noncondensable gas mass fraction and the aspect ratio of the condensertube. The empirical correlation was applied to the MARS-KS code to replace the default Colburn-Hougenmodel. The various thermal-hydraulic parameters during the operation of the PCCS follonwing a large-breakloss-of-coolant-accident were analyzed. The transient pressure behavior inside the containment from theMARS-KS with the empirical correlation was compared with calculated with the Colburn-Hougen model.