• 소음진동
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• 제5권1호
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• pp.95-106
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• 1995

Flow-induced vibration in heat exchanger (or fuel rod) in nuclar power plant can cause dynamic interactions between tubes and tube supports resulting in fretting-wear. To increase the reliability and design life of heat exchanger components, design criteria that establish acceptable limits of vibration and minimize fretting wear are necessary. The fretting-wear rate is dependent upon material combination, contact configuration, environmental conditions and tube-to tube support dynamic interaction. It is demostrated that the fretting -wear rate correlates well with tube-to-support contact force or work rate. The tube-to-support dynamic interaction, which consists of dynamic contact forces and tube motion, is used to relate single-span wear data to real heat exchanger configurations consisting of multi-span tube bundles. This paper describes the test facility to measure tube-to-support dynamic impact force and reports its dynamic characteristics through the four impact tests - a force transduces independent and external impact tests, central ring inside impact test and additional cylinder impact test. Through the tests the impact parameter change dependent upon the material difference of impacting ball is studied, and the impact parameters of Force Transducer Assembly components are measured. And also the dynamic behavior of Force Transducer Assembly is analyzed. The force measurement technique herein is shown to provide a reasonable measure of dynamic contact forces.

• 한국수산과학회지
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• 제38권3호
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• pp.158-163
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• 2005

This paper deals with the histology of the barbels of striped sea catfish, Plotosus lineatus (Thunberg). This fish have eight noticeable barbels of two pairs on their maxillary and mandibular. Each barbel is composed of an epidermis, dermis and a central rod of cartilage. The epidermis in the middle part of the maxillary barbel is thicker than those on other parts, and formed of stratified epithelium which contains many cutaneous taste buds and a few small club cells. Number of taste buds increase on the middle and posterior part of each barbel. The dermis consists of loose connective tissue fibers which encloses blood vessels and bundles of nerve fibers. The barbels of this fish can be categorized into stiff and flexible types and are accessory, feeding and sensory structures. Thus we substantiate that they are gustatory receptor organs for this fish.

• 한국방사선학회논문지
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• 제11권7호
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• pp.571-578
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• 2017

원자로 내 사고발생 시 냉각수의 비등으로 기포가 발생하고, 기포율을 측정하기 위하여 열수력 안전 분야에서는 주로 Optical Fiber Probe(OFP)나 광학 카메라를 이용하여 측정하지만 기하학적 구조의 한계로 인해 $17{\times}17$ 배열의 봉 다발 내에 장비를 설치하는 것에는 어려움이 있다. 본 연구는 예비 연구로서 봉 다발에 적용하기 전 X선 시스템과 다양한 모사 팬텀을 이용하여 연구 가능성 평가를 수행하였다. 라디오그라피 및 토모그라피 실험을 통해 X선 발생 장치의 관전압 130 kVp, 관전류 1 mA가 적합하였다. 또한, 기포 해상도 팬텀을 통해 가시적으로 1 mm 크기의 구멍에 대해 측정이 가능하였으며 막대 팬텀을 이용한 대조도 평가의 경우 프레온 내부에서 대조도가 상대적으로 떨어짐을 확인할 수 있었다. 그러나 영상 재구성 시 일그러짐이 없는 좋은 영상을 획득할 수 있었다. 기포 발생 팬텀 실험을 통해 기포의 유동 방향 확인 및 단층 영상을 획득할 수 있었고, Image J 툴을 이용하여 하나의 단층영상에 대해 18 %의 기포율을 측정할 수 있었다. 본 연구는 핵연료 주변 기포율 측정을 위한 선행 연구를 수행하였고 지속적인 연구를 위한 기초 연구로서 활용할 수 있을 것이다.

• 태양에너지
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• 제13권1호
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• pp.11-21
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• 1993

이차원(二次元) 충돌공기분류계(衝突空氣噴流系)에서 흐름방향과 수직(垂直)이 되게 설치한 평판전열면(平板傳熱面) 전방(前方)에 난류촉진체(亂流促進體)인 정4각(正4角) 로드군(群)(로드폭=4mm, 로드피치=50mm)을 설치하고 로드와 전열면(傳熱面)사이의 간극(間隙)(C=1, 2, 4, 6mm), 노즐출구와 전열면간(傳熱面間) 거리(H/B=2, 6, 10, 14) 및 Re수($Re=6.410{\times}10^3{\sim}5.769{\times}10^4$)를 변화시켜 실험한 결과, 평판(平板)에서 열전달계수(熱傳達系數)의 감소율이 큰 영역에서도 로드를 설치하므로써 높은 열전달계수(熱傳達係數)를 얻을 수 있었으며, 실험범위내의 Re수와 H/B에 대하여 열전달계수(熱傳達係數)가 최대(最大)가 되는 최적간극(最適間隙)은 C=1mm이고, 최대(最大) 열전달증진율은 H/B=2, C=1mm에서 로드를 설치하지 않은 평판(平板)보다 약 43% 증진한다.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.842-848
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• 2022

Parametric studies of heat transfer and fluid flow are very important research of interest because the design and operation of fluid flow and heat transfer systems are guided by these parametric studies. The safety of the system operation and system optimization can be determined by decreasing or increasing particular fluid flow and heat transfer parameter while keeping other parameters constant. The parameters that can be varied in order to determine safe and optimized system include system pressure, mass flow rate, heat flux and coolant inlet temperature among other parameters. The fluid flow and heat transfer systems can also be enhanced by the presence of or without the presence of particular effects including gravity effect among others. The advanced Generation IV reactors to be deployed for large electricity production, have proven to be more thermally efficient (approximately 45% thermal efficiency) than the current light water reactors with a thermal efficiency of approximately 33 ℃. SCWR is one of the Generation IV reactors intended for electricity generation. High Performance Light Water Reactor (HPLWR) is a SCWR type which is under consideration in this study. One-eighth of a proposed fuel assembly design for HPLWR consisting of 7 fuel/rod bundles with 9 coolant sub-channels was the geometry considered in this study to examine the effects of system pressure and mass flow rate on wall and fluid temperatures. Gravity effect on wall and fluid temperatures were also examined on this one-eighth fuel assembly geometry. Computational Fluid Dynamics (CFD) code, STAR-CCM+, was used to obtain the results of the numerical simulations. Based on the parametric analysis carried out, sub-channel 4 performed better in terms of heat transfer because temperatures predicted in sub-channel 9 (corner subchannel) were higher than the ones obtained in sub-channel 4 (central sub-channel). The influence of system mass flow rate, pressure and gravity seem similar in both sub-channels 4 and 9 with temperature distributions higher in sub-channel 9 than in sub-channel 4. In most of the cases considered, temperature distributions (for both fluid and wall) obtained at 25 MPa are higher than those obtained at 23 MPa, temperature distributions obtained at 601.2 kg/h are higher than those obtained at 561.2 kg/h, and temperature distributions obtained without gravity effect are higher than those obtained with gravity effect. The results show that effects of system pressure, mass flowrate and gravity on fluid flow and heat transfer are significant and therefore parametric studies need to be performed to determine safe and optimum operating conditions of fluid flow and heat transfer systems.

• 한국어류학회지
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• 제17권1호
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• pp.36-42
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• 2005

한국의 메기과 (Siluridae) 어류의 수염을 조직학적으로 조사하였다. 메기, Silurus asotus의 상악 수염은 연골성 중축을 감싸는 진피와 표피로 구성 되었다. 표피층에는 점액세포, 과립형세포 및 미뢰가 있었다. 세포질이 약한 호염기성을 보이는 점액세포와 호염기성을 보이는 미뢰는 각각 표피의 표면과 표피 말단 부위에 위치 하였다. 표피와 진피는 기저막으로 구분되며 진피는 소성결합조직으로 구성 되었으며 신경세포와 혈관이 내재하고 있었다. 수염의 가장 내부에 연골성 중축이 존재 하였으며 근육층으로 둘러싸여 있었다. 미유기, S.microdorsalis의 상악 수염 구조는 메기의 상악 수염 구조와 비교시 별다른 차이는 보이지 않았으나, 상악 상부와 하부에서의 표피 % 두께 및 상악 상부와 중부에서의 미뢰 수에 있어 미유기는 메기에 비해 차이를 보였다. 본 연구결과 메기와 미유기의 상악 수염은 딱딱하고 굴절성형(stiff and flexible type)으로 파악 되었다.

• 전기화학회지
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• 제14권4호
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• pp.196-200
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• 2011

본 연구에서는 니오븀 산화물을 비교적 저온에서 단시간 동안의 양극산화법을 통해 제조하였다. 이때, 전해질로는 NaF와 HF를 혼합하여 사용하였으며, 20~120 V의 다양한 전압 조건에 따라 생성되는 니오븀 산화물의 미세구조를 관찰하였다. 일반적으로 니오븀 금속의 양극산화 시 초기에 생성된 니오븀 산화물은 무정형 구조이나 반응이 경과함에 따라 점차 결정형 산화물로 성장하게 된다. 이러한 산화물은 XRD 분석을 통하여 결정형의 $Nb_2O_5$ 임을 확인하였고, FE-SEM 분석결과, 그 표면은 매우 밀집된 형태의 나노로드로 이루어진 마이크로콘 산화물임을 알 수 있었다. 적절한 공정변수로 제조된 니오븀 산화물은 마이크로콘 구조 전체 표면에 걸쳐 동일한 크기를 갖는 나노로드 다발을 형성하고 있으며, 이러한 나노 구조는 또한 넓은 표면적을 기대할 수 있어 염료감응 태양전지나 바이오 소재 등에 대한 다양한 분야에 응용될 수 있을 것으로 기대된다.

• 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.

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.493-520
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• 2009

During the last four decades, 16 Pressurized Water Reactors (PWR) and 4 Pressurized Heavy Water Reactors (PHWR) have been constructed and operated in Korea, and nuclear fuel technology has been developed to a self-reliant state. At first, the PWR fuel design and manufacturing technology was acquired through international cooperation with a foreign partner. Then, the PWR fuel R&D by Korea Atomic Energy Research Institute (KAERI) has improved fuel technology to a self-reliant state in terms of fuel elements, which includes a new cladding material, a large-grained $UO_2$ pellet, a high performance spacer grid, a fuel rod performance code, and fuel assembly test facility. The MOX fuel performance analysis code was developed and validated using the in-reactor test data. MOX fuel test rods were fabricated and their irradiation test was completed by an international program. At the same time, the PWR fuel development by Korea Nuclear Fuel (KNF) has produced new fuel assemblies such as PLUS7 and ACE7. During this process, the design and test technology of fuel assemblies was developed to a self-reliant state. The PHWR fuel manufacturing technology was developed and manufacturing facility was set up by KAERI, independently from the foreign technology. Then, the advanced PHWR fuel, CANFLEX(CANDU Flexible Fuelling), was developed, and an irradiation test was completed in a PHWR. The development of the CANFLEX fuel included a new design of fuel rods and bundles.. The nuclear fuel technology in Korea has been steadily developed in many national R&D programs, and this advanced fuel technology is expected to contribute to a worldwide nuclear renaissance that can create solutions to global warming.

• 한국수의병리학회지
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• 제2권1호
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• pp.53-60
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• 1998

A fourteen-month-old Holstein bull from a private cattle fattening farm at Ansung county in Kyunggi Province Korea was submitted on August 2nd 1997, for examination at the Pathology Division of the National Veterinary Research Institute. The bull died within 24 hours after developing clinical signs of abrupt inertia, complete anorexia high fever(40.3℃) diffuse severe emphysematous swelling of upper part of the right hind leg lateral recumbancy and paralysis. At necropsy diffuse severe subcutaneous redness and influx of serosanguinous exudate containing gas bubbles had accumulated under the thorax right hip and upper region of right hind leg. Muscles in upper right hind leg were blackish to dark red and yellowish brown in color. Muscle bundles were dry and separated by gas bubbles and serosanguinous fluids and muscles sections from affected regions floated in water. Histopathologically muscle fibers were partially or entirely degenerated fragmented and separated by exudate and gaseous substance mixed with polymorphonuclear cells. Blood vascular walls in affected regions showed severe acute fibrinoid necrosis. Typical large rod-shaped bacteria with or without oval central to subterminal spores were frequently observed in tissue sections stained with H-E and Gram stain. The large Gram-positive anaerobic endospore-producing rods were isolated from the suspension of muscle lesions. Isolated bacteria were identified as Clostridium(CL) chauvoei and CL. sordellii by biochemical tests. This case was diagnosed as blackleg based on the typical clinical signs gross finding histopathological observation and bacteriological results. This is the first case report on blackleg associated with Cl. chauvoei and Cl. sordellii in Holstein cattle in Korea.