• Wind and Structures
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• 제22권6호
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• pp.617-633
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• 2016

In this paper, the analysis of hyperbolic cooling tower on elastic subsoil exposed to unsymmetrical wind loading is presented. Modified Vlasov foundation model is used to determine the soil parameters as a function of vertical deformation profile within subsoil. The iterative parameter updating procedure involves the use of Open Application Programming Interface (OAPI) feature of SAP2000 to provide two way data flow during execution. A computing tool coded in MATLAB employing OAPI is used to perform the analysis of hyperbolic cooling tower with supporting columns over a hollow annular raft founded on elastic subsoil. The analysis of such complex soil-structure system is investigated under self-weight and unsymmetrical wind load. The response of the cooling tower on elastic subsoil is compared with that of a tower that its supporting raft foundation is treated as fixed at the base. The results show that the effect of subsoil on the behavior of cooling tower is considerable at the top and bottom of the wall as well as supporting columns and raft foundation. The application of a full-size cooling tower has demonstrated that the procedure is simple, fast and can easily be implemented in practice.

• 한국항공우주학회지
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• 제34권2호
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• pp.68-74
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• 2006

가스터빈 슬링거 연소기의 연소특성을 연구하기 위한 실험적 연구를 수행하였다. 연소실험을 위한 시험리그를 제작하여 한국항공우주연구원의 연소시험설비에 설치하였다. 점화성능 시험결과 점화한계에 영향을 주는 두개의 중요한 인자를 발견할 수 있었다. 첫 번째는 연료노즐의 회전수이고, 두 번째는 질량유량이다. 좋은 점화성능을 가지기 위해서는 연료노즐의 회전속도와 공기유량을 증가시킴으로서 가능하다. 연소성능 시험결과 연소효율은 99.6%, 패턴 팩터는 15%, 프로파일 팩터는 3%로 측정 되었다. 연구결과 슬링거 연소기의 점화와 연소특성은 기존의 환형 연소기에 비하여 상당한 차이점을 가지고 있음을 알 수 있었다.

• 한국추진공학회지
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• 제23권2호
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• pp.38-45
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• 2019

본 연구에서는 항공용 가스터빈의 연소실에서의 연소불안정 해석을 위한 고유값 도출을 목적으로 하는 1D 네트워크 모델을 개발하였다. 모델은 면적 변화가 있는 음향 네트워크 요소들 사이의 각종 지배 방정식을 통하여 개발되었고, 이를 이용하여 현재 개발 중인 복잡한 유로 형상을 갖는 실제 항공용 가스터빈 연소기에서의 음향장 해석에 적용되었다. 본 모델을 통하여 도출된 음향장 해석 결과는 3차원 유한요소해석 기반의 헬름홀츠 솔버의 계산 결과와 비교하였다.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.959-965
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• 2024

The High Temperature Test Unit (HTTU) was an experimental set-up to conduct separate and integral effects tests of the Pebble Bed Modular Reactor (PBMR) core. The annular core consisted of a randomly packed bed of uniform spheres. Natural convection tests using both nitrogen and helium, and forced convection tests using nitrogen, were conducted. The maximum material temperature achieved during forced convection testing was 1200 ℃. This paper presents the numerical analysis of the flow and temperature distribution for a forced convection test using 3D CFD as well as a 1D systems-CFD computer code. Several modelling approaches are possible, ranging from a fully explicit to a semi-implicit method that relies on correlations of their associated phenomena. For the comparison between codes, the analysis was performed using a porous media approach, where the conduction and radiative heat transfer were lumped together as an effective thermal conductivity and the convective heat transfer was correlated between the solid and gas phases. The results from both codes were validated against the experimental measurements. Favourable results were obtained, in particular by the systems-CFD code with minimal computational and time requirements.

• Journal of Advanced Marine Engineering and Technology
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• 제10권2호
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• pp.156-164
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• 1986

In the case of boiling on high temperature wall, vapor film covers fully or parcially the surface. This phenomenon, film boiling or transition boiling, is very important in the surface heat treatment of metal, design of cryogenic heat exchanger and emergency cooling of nuclear reactor. Mainly supposed hydraulic-thermal accidents in nuclear reactor are LCCA (Loss of Coolant Accident) and PCM (Power-Cooling Mismatch). Recently, world-wide studies on reflooding of high temperature rod bundles after the occurrence of the above accidents focus attention on wall temperature history and required time in transient cooling process, wall superheat at rewet point, heat flux-wall superheat relationship beyond the transition boiling region, and two-phase flow state near the surface. It is considered that the further systematical study in this field will be in need in spite of the previous results in ref. (2), (3), (4). The paper is the study about the fast transient cooling process following the wall temperature excursion under the CHF (Critical Heat Flux) condition in a forced convective subcooled boiling system. The test section is a vertically arranged concentric annulus of 800 mm long and 10 mm hydraulic diameter. The inner tube, SUS 304 of 400 mm long, 8 mm I.D, and 7 mm O.D., is heated uniformly by the low voltage AC power. The wall temperature measurements were performed at the axial distance from the inlet of the heating tube, z=390 mm. 6 chromel- alumel thermocouples of 76 .mu.m were press fitted to the inner surface of the heating tube periphery. To investigate the heat transfer characteristics during the fast transient cooling process, the outer surface (fluid side) temperature and the surface heat flux are computed from the measured inner surface temperature history by means of a numerical method for inverse problems of transient heat conduction. Present cooling (boiling) curve is sufficiently compared with the previous results.

• 대한기계학회논문집A
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• 제35권4호
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• pp.417-424
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• 2011

핵연료집합체는 상단고정체, 하단고정체, 지지격자체, 제어관/계측관과 핵연료봉의 5 가지 주요 구성품으로 이루어져 있다. 여기서 상/하단고정체는 다른 구성품과 달리 ASME, Section III, Division 1 - Subsection NB 의 운전조건 A, B 에서의 stress intensity limits 를 만족하여야 한다. 이중냉각 핵연료집합체는 집합체당 출력을 증가시키기 위해서 기존의 가압경수로용 핵연료집합체에서 핵연료봉의 배열과 위치를 변화시켰는데 이로 인하여 핵연료봉 내/외부유로로 냉각수가 잘 흐를 수 있도록 상/하단고정체의 유로판의 형상을 수정하여야 한다. 본 논문에서는 설계하중조건에 대하여 수정된 상단고정체 유로판의 건전성평가를 위해 수행한 응력선형화과정을 자세히 설명하고 평가결과에 대하여 기술하였다.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1995년도 춘계학술발표회 초록집
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• pp.185-198
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• 1995

This is an experimental study conducted to visualize the nucleate boiling phenomena and flow regimes occurring inside the liquid pool in a closed two-phase thermosyphon. To meet this purpose, an annular-type thermosyphon was designed and manufactured using a glass tube and a stainless steel tube, being assembled axisymmetrically. The heat to be supplied to the working fluid is generated within a very thin layer of stainless steel tube wall by applying a high frequency electromagnetic field through the induction coil, axisymmetrically set around the evaporator zone. Some important results were as follows ; 1) Considering the structural complexity of the tested thermosyphon, it showed good performance for the range of heat flux 2＜ q" ＜25kW/$m^2$ and saturation vapor pressure, 0.1＜Pv＜1.1bar 2) different type of nucleating boiling regimes were observed as described below, -Pulse boiling regime : Flow pattern changed cyclically with time during 1 cycle of pulse boiling process. The onset of Nucleation was followed by expulsive growing of vapor bubble, resulting in the so called blow-up phenomenon, massive expulsion of large amount of liquid around the bubble. -Transient : Some spherical vapor bobbles were observed growing out from 2~3 nucleating sites, that was dispersed at the lower part of the heated tube wall in the liquid pool. But the rest upper region above the nucleating sites were filled with churns or bubbles of vapor. -Continuous nucleate boiling regime : The whole zone of evaporator was filled with lots of spherical vapor bubbles, and the bubbles showed tendency to decrease in diameter as the heat flux increased.ased.

• 한국해양공학회지
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• 제25권5호
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• pp.15-20
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• 2011

This study carried out a series of experiments involving impact tests (Drop Weight type & Charpy type with a standard specimen and newly designed I-type specimen), hardness tests, and fracture surface observations of French-made roll shell steel (F), abnormal roll shell steel (M), reheated roll shell steel (R), and S25C steel under heat treatment conditiAn experimental study was carried out to study the solid-liquid mixture upward hydraulic transport of solid particles in vertical and inclined annuli with a rotating inner cylinder. The lift forces acting on a fluidized particle play a central role in many important applications such as the removal of drill cuttings in horizontal drill holes, sand transport in fractured reservoirs, sediment transport, the cleaning of particles from surfaces, etc. In this study a clear acrylic pipe was used to observe the movement of solid particles. Annular velocities varied from 0.4 to 1.2 m/s. The effect of the annulus inclination and drill pipe rotation on the carrying capacity of a drilling fluid, particle rising velocity, and pressure drop in a slim hole annulus were measured for fully-developed flows of water and aqueous solutions of CMC (sodium carboxymethyl cellulose) and bentonite. The rotation of the inner cylinder was efficient at carrying particles to some degree. For a higher particle volume concentration, the hydraulic pressure loss of the mixture flow increased because of the friction between the wall and solids or between solids.

• Nuclear Engineering and Technology
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• 제51권7호
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• pp.1738-1748
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• 2019

Previous research has shown that the inclined condition has an impact on the natural circulation (natural circulation) mode operation of Floating Nuclear Power Plant (FNPP) mounted on the movable marine platform. Due to its compact structure, small volume, strong maneuverability, the Integral Pressurized Water Reactor (IPWR) is adopted as marine reactor in general. The OTSGs of IPWR are symmetrically arranged in the annular region between the reactor vessel and core support barrel in this paper. Therefore, many parallel natural circulation loops are built between the core and the OTSGs primary side when the main pump is stopped. and the inclined condition would lead to discrepancies of the natural circulation drive head among the OTSGs in different locations. In addition, the flow rate and temperature nonuniform distribution of the core caused by inclined condition are coupled with the thermal hydraulics parameters maldistribution caused by OTSG group operating mode on low power operation. By means of the RELAP5 codes were modified by adding module calculating the effect of inclined, heaving and rolling condition, the simulation model of IPWR in inclined condition was built. Using the models developed, the influences on natural circulation operation by inclined angle and OTSG position, the transitions between forced circulation (forced circulation) and natural circulation and the effect on natural circulation operation by different OTSG grouping situations in inclined condition were analyzed. It was observed that a larger inclined angle results the temperature of the core outlet is too high and the OTSG superheat steam is insufficient in natural circulation mode operation. In general, the inclined angle is smaller unless the hull is destroyed seriously or the platform overturn in the ocean. In consequence, the results indicated that the IPWR in the movable marine platform in natural circulation mode operation is safety. Selecting an appropriate average temperature setting value or operating the uplifted OTSG group individually is able to reduce the influence on natural circulation flow of IPWR by inclined condition.

• 청정기술
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• 제13권2호
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• pp.151-158
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• 2007

프레온계 냉매의 지구온난화와 오존층파괴 문제로 인해 대체냉매로서 R-410A가 주목을 받고 있다. 이러한 대체냉매를 세관에 적용시킬 경우 효율을 향상시킬 뿐만 아니라 지구환경에 미치는 영향을 감소시키고, 대기를 청정하게 만드는 기술 및 방안으로 각광 받고 있다. 따라서 본 연구에서는 R-22의 대체냉매로 각광받고 있는 R-410A의 세관응축기 내에서의 응축열전달 특성에 대해 실험적으로 고찰하고자 하였다. 실험장치는 유동양식, 열전달, 압력강하 특성을 파악할 수 있도록 제작되었고, 주요 구성품은 냉매펌프, 증발기, 응축기(시험부), 사이트 글라스(가시화부), 압력탭, 측정장치 등이다. 시험부의 내관은 내경 3.36 mm와 5.35 mm인 수평평활 동관이다. 실험변수들의 범위로서 질량유속 $200{\sim}500\;kg/m^2s$이고, 열유속은 $1.0{\sim}2.4\;kW$이다. R-410A의 응축열전달 계수가 R-22에 비해 최대 5% 정도 높은 것을 알 수 있었다. 세관 내 R-410A와 R-22의 유동양식은 환상류 영역이 지배적으로 나타남을 관찰하였고, 건도가 0.2 이하인 영역에서는 성층류가 나타남을 확인할 수 있었다. 내경 3.36 mm의 압력강하가 내경 5.35 mm에 비해 $30{\sim}50%$정도 높았다. 종래의 응축 열전달 상관식과 실험데이터를 비교한 결과, Fujii의 상관식과 최대 40%이내에서 일치하였다.