• 한국태양에너지학회 논문집
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• 제30권4호
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• pp.92-99
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• 2010

The purpose of this study is to apply pressurized plenum under floor air conditioning system to office areas to understand characteristics of indoor thermal environment based on forms of diffusers. For doing this, the author conducted experiment of module measurement, and based on the results, analyzed indoor temperature distribution and velocity distribution based on direction of diffusion by using Computational Fluid Dynamics(CFD), and estimated the Predicted Mean Vote(PMV) of residents based on forms of diffusers to present the optimal air conditioning of the pressurized plenum under floor air conditioning system in heating. The results of this study are as follows. First, as for forms of diffusers, distributed diffusers rather than conical and grill diffusers were favorable in maintaining $24^{\circ}C$, the established temperature in heating, were active in velocity flowing, and were wide in a radius of diffusion. Second, as for position of pressurizing, the difference between upper and lower temperature was wider in center, lateral, and dispersed pressurizing (in order). As for velocity distribution, the velocity was more increased in lateral, center, and dispersed pressurizing(in order), indicating that dispersed pressurizing maintained uniform thermal environment. Third, as for diffusion direction, mixed direction showed less difference between upper and lower temperature and the difference in velocity between center and lateral part was 0.01m/1, indicating that it maintained uniform thermal environment. Fourth, as for the PMV of residents based on the forms of diffusers, the dispersed type showed(+) values above (0) when applied variably based on the position of diffuser, presenting thermal feeling of "being comfortable" to residents.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2009년도 제33회 추계학술대회논문집
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• pp.231-235
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• 2009

본 연구의 목적은 실제로 서인천 발전본부에서 운용하고 있는 GE 7FA+e DLN 2.6 가스터빈 연소기의 연소특성과 배기배출물에 대한 제어 연구를 소개하고 모형 가스터빈 연소기의 연소동특성 및 연소불안정 현상을 확인하고자 한다. 모형 연료노즐은 실제의 1/3 크기로 상사하여 제작되었고, 실제 노즐과 동일한 각도의 2단 스월러(swirl vane)를 가지고 있다. Plenum과 연소기의 형상은 실 가스터빈과 유사한 음향학적 특성을 가질 수 있도록 설계되었고 실험은 공기온도, 노즐출구 속도, 당량비, 연소실 길이를 변수로 이루어졌으며, 그 결과 연소실의 연소불안정 mode는 각각의 실험 변수에 따라서 연소실의 공진주파수의 영향, 연소온도와 공기-연료 혼합기 분포에 의해서 mode가 전이되는 현상을 확인하였다.

• Nuclear Engineering and Technology
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• 제32권4호
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• pp.395-409
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• 2000

Parametric studies were performed to assess the sensitivity in determining the maximum in-vessel heat removal capability from the core material relocated into the lower plenum of the reactor pressure vessel (RPV）during a core melt accident. A fraction of the sensible heat can be removed during the molten jet delivery from the core to the lower plenum, while the remaining sensible heat and the decay heat can be transported by rather complex mechanisms of the counter-current flow limitation (CCFL) and the critical heat flux (CHF）through the irregular, hemispherical gap that may be formed between the freezing oxidic debris and the overheated metallic RPV wall. It is shown that under the pressurized condition of 10MPa with the sensible heat loss being 50% for the reactors considered in this study, i.e. TMI-2, KORI-2 like, YGN-3&4 like and KNGR like reactors, the heat removal through the gap cooling mechanism was capable of ensuring the RPV integrity as much as 30% to 40% of the total core mass was relocated to the lower plenum. The sensitivity analysis indicated that the cooling rate of debris coupled with the sensible heat loss was a significant factor The newly proposed heat removal capability map (HRCM) clearly displays the critical factors in estimating the maximum heat removal from the debris in the lower plenum. This map can be used as a first-principle engineering tool to assess the RPV thermal integrity during a core melt accident. The predictive model also provided ith a reasonable explanation for the non-failure of the test vessel in the LAVA experiments performed at the Korea Atomic Energy Research Institute (KAERI), which apparently indicated a cooling effect of water ingression through the debris-to-vessel gap and the intra-debris pores and crevices.

• 한국소음진동공학회논문집
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• 제20권12호
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• pp.1139-1146
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• 2010

The indoor noise of the naval vessel is very important related to the optimum environmental conditions for crews as well as the ability of fighting power of antisubmarine. Especially, sonar equipment room is one of the rooms where require to be silent because the informations of the underwater noise are collected and analyzed in there. In this paper, the sound reduction of the TASS console, one of the main noise sources in a sonar equipment room for a typical naval vessel, is described. The noise source of this TASS console is the flowing noise of cooling fan. In order to reduce this kind of noise, the plenum chamber and acoustic elbow were developed. Related to the development of the plenum chamber, the area of the air-outlet and sound absorption of the inner lining were investigated experimentally with the evaluation system of the sound insertion loss. Acoustic elbow was also manufactured and evaluated with the evaluation system of the sound insertion loss. Finally, in order to evaluated the ability of noise reduction of the plenum chamber and acoustic elbow, the indoor noise of the sonar equipment was measured when they were appled to TASS console.

• 한국음향학회지
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• 제20권6호
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• pp.66-74
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• 2001

본 논문에서는 노심 용융물과 원자로 용기하부 반구내벽 사이의 간격형성 여부 및 간극의 열적 영향을 측정하기 위한LAVA (Lower-plenum arrested vessel attack) 실험에서 초고온상태에 있는 노심 용융물의 온도를 측정할 목적으로 초고온 온도측정 시스템을 개발하였다. 본 연구에서는 제안된 이론의 유용성을 확인할 목적으로 개발한 초음파 자왜 센서 시스템을 이용하여 2300℃까지의 온도를 측정함으로써 실험을 통해 개발된 시스템의 효율성을 증명하였다.

• 한국자동차공학회논문집
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• 제5권6호
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• pp.175-182
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• 1997

The purpose of this study is to investigate the effects of intake manifold shapes to improve the engine performance in a 3-cylinder LPG engine with a closed loop fuel supply system. To know the flow resistance of intake manifolds with shape, the intake negative pressure of each runner in intake manifolds were measured by using the digital pressure meter at each driving condition. And, the engine torque and power have been measured with an engine dynamometer while adjusting the optimal fuel consumption ratio with a solenoid driver. As 속 results form this experiment, the torque characteris- tics were more improved with the plenum chamber(B type intake manifold) than with the banana type(A type intake manifold). The torque characteristics were improved at mid-engine speed(rpm) range as the inner diameter of the intake manifold became smaller. And also the optimum volume among the examined plenum chamber volume was 0.74 times(590cc) the displacement of the test engine.

• Nuclear Engineering and Technology
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• 제37권6호
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• pp.557-564
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• 2005

Air-water countercurrent flow limitation at perforated plates with four holes was investigated in a vertical tank to see the effects of the plate thickness, the number of hole, and the diameter of the hole on the onset of CCFL. The thickness of plates was 1 cm and 4 cm, with a relatively large hole diameter of 5 cm. The collapsed water level formed on the perforated plate and its distribution in the upper plenum were measured. The gas flow rate in the multi-hole plate is relatively higher than one in the single tube because some of holes in the multi-hole plate provide a flow path fur liquid with less air-liquid resistance than in the single tube. The onset of CCFL occurred at nearly the same air flow rate regardless of the plate thickness. The negligible effect of the plate thickness on CCFL means that the flooding is initiated at the top of the plate rather than at its bottom. It turns out that $j_k$ and $K_k$ better fit the data than $H_k$ when hole diameter is greater than 2.86 cm. In our experimental ranges, the collapsed water levels at the onset of CCFL ranged from 7.5 cm to 10.5 cm. There was no three dimensional distribution of water level before and after the onset of CCFL.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.93-102
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• 2021

The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the safety of nuclear power plant. The flow distribution and mixing characteristics in the pressurized reactor vessel for the 1000MWe advanced pressurized water reactor is analyzed by using Computational Fluid Dynamics (CFD) method in this study. The geometry model of the full-scaled reactor vessel is built, which includes the cold and hot legs, downcomer, lower plenum, core, upper plenum, top plenum, and is verified with some parameters in DCD. Under normal condition, it is found that the flow skirt, core plate holes and outlet pipe cause pressure loss. The maximum and minimum flow coefficient is 1.028 and 0.961 respectively, and the standard deviation is 0.019. Compared with other reactor type, it shows relatively uniform of the flow distribution at the core inlet. The coolant mixing coefficient is investigated with adding additional variables, showing that mass transfer of coolant occurs near the interface. The coolant mainly distributes in the 90° area of the corresponding core inlet, and mixes at the interface with the coolant from the adjacent cold leg. 0.1% of corresponding coolant is still distributed at the inlet of the outer-ring components, indicating wide range of mixing coefficient distribution.

• 디지털콘텐츠
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• 8호통권3호
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• pp.59-60
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• 1993

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.144.2-144
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• 2001