• 제목/요약/키워드: Cooling capability

검색결과 173건 처리시간 0.028초

자유유동 전기이동법에 의한 대두단백질 분리 (Separation of Soybean Protein by Free-flow Electrophoresis)

  • 한재갑;류화원
    • KSBB Journal
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    • 제10권1호
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    • pp.63-70
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    • 1995
  • 실험실에서 자체 제작한 자유유통 전기이동 장치 에서 등전집속법을 이용한 대두 단백질의 분리를 통 해 운전 조건들이 분리에 미치는 영향을 조사하였 다. 매 실험마다 pH, 전기전도도, uv 흉광도 (280nm) 등을 측정하였고 시료의 순도는 SDS­P PAGE 분석을 통해 점검하였다. Tris와 boric acid로 처리한 대두단백질 추출액에 g glutamic acid, histidine, argmme, glycine 등 아 미노산 각 ImM과 dipeptide로 glycyl-glycine 2mM, 배경 전해액으로서 KCI ImM로 구성된 시료 의 완충액을 혼합하여 시료로 사용하였다. 분리막을 셀룰로오스 아세테이트를 사용할 경우 pH는 양극쪽에서 3, 음극쪽에서 8 정도의 값을 보였으며 2개의 변곡점을 나타내었다. 가해준 전압은 3 300V에서 lOOOV의 범위였으며 전압이 높을수록 더 나은 분리도를 얻었으나 전압을 더 높일 경우 과도한 Joule열의 발생으로 인해 한계가 있었다. 시간이 지남에 따라 단백질들은 분리조 중앙 부근에서 집속이 일어났으며 pH와 전기전도도의 변화로부터 분리 조내의 이온들이 막을 통해 전극쪽으로 이통해 가고 있음을 알 수 있었다. 완충용액의 농도를 5배로 증 가시킬 경우 300V에서 좋은 집속을 얻었으냐 10배 이상으로 농도를 높일 경우에는 분리조 입구와 출구 의 유체 온도차가 $25^{\circ}C$ 이상이 되어 단백질의 변성 이 일어날 수 있어 더 높일 수 없었다. 이온교환막을 사용할 경우 이온의 분극화현상을 일으켜 U자 형태 의 전기전도도 분포를 나타내었다. 아미노산 혼합물 대신 상용의 ampholyte를 사용하더라도 분리도에 있어 큰 차이가 없었다.

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플라즈마 용융 공정시의 폐열 재활용 연구 (A Study on Waste Heat Recycling of Plasma Melting System)

  • 김성중
    • 유기물자원화
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    • 제14권3호
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    • pp.85-90
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    • 2006
  • 플라즈마 용융로에 설치된 폐열 보일러를 실측치와 근접한 모의 보일러를 설계하여 CFD(전산유체역학) 프로그램을 이용하여 얻어진 보일러 내에서의 유해가스발생 및 열 유동현상에 대한 열 설계 능력 확보와 폐열보일러 효율 개선에 대한 연구를 수행하는데 목적이 있다. 보일러 내에서의 온도변화 및 연소가스의 공기 유동, 부식성 가스의 영향으로 인해 보일러 내부에서의 부식위치 및 클링커 생성여부에 관한 연구를 통해 효율적인 보일러의 구조 설계 및 에너지 재활용방안에 이용하고자 한다. 연구결과 플라즈마 용융로에 설치된 보일러 설비는 2차 연소로 출구에서 배출되는 약 $1,200^{\circ}C$의 연소가스를 약 $450^{\circ}C$까지 냉각시킬 수 있는 설계조건을 만족시켰다. 반면 유해가스 유동 결과 보일러 입구 부분의 상단부와 하단부에 부식성 가스 (SOx, HCl)의 영향으로 인하여 부식 및 클링커 생성이 보일러의 다른 위치보다 쉽게 발생될 것으로 예상된다. 이로 인해 보일러 내 외관벽의 부식으로 보일러의 수명 단축 및 효율적인 폐열을 재활용 할 수 없다고 예상된다. 이에 따른 저온 및 고온 부식 방지대책에 대한 세심한 고려가 필요하다 하겠다.

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심자도용 접선성분자장 측정방식 스퀴드 센서열 설계 (Design of a SQUID Sensor Array Measuring the Tangential Field Components in Magnetocardiogram)

  • 김기웅;이용호;권혁찬;김진목;김인선;박용기;이규원
    • Progress in Superconductivity
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    • 제6권1호
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    • pp.56-63
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    • 2004
  • We consider design factors for a SQUID sensor array to construct a 52-channel magnetocardiogram (MCG) system that can be used to measure tangential components of the cardiac magnetic fields. Nowadays, full-size multichannel MCG systems, which cover the whole signal area of a heart, are developed to improve the clinical analysis with high accuracy and to provide patients with comfort in the course of measurement. To design the full-size MCG system, we have to make a compromise between cost and performance. The cost is involved with the number of sensors, the number of the electronics, the size of a cooling dewar, the consumption of refrigerants for maintenance, and etc. The performance is the capability of covering the whole heart volume at once and of localizing current sources with a small error. In this study, we design the cost-effective arrangement of sensors for MCG by considering an adequate sensor interval and the confidence region of a tolerable localization error, which covers the heart. In order to fit the detector array on the cylindrical dewar economically, we removed the detectors that were located at the corners of the array square. Through simulations using the confidence region method, we verified that our design of the detector array was good enough to obtain whole information from the heart at a time. A result of the simulation also suggested that tangential-component MCG measurement could localize deeper current dipoles than normal-component MCG measurement with the same confidence volume; therefore, we conclude that measurement of the tangential component is more suitable to an MCG system than measurement of the normal component.

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열전소자를 이용한 발광다이오드의 발열 온도 제어 (Control of Heat Temperature in Light Emitting Diodes with Thermoelectric Device)

  • 한상호;김윤중;김정현;김동준;정종윤;김성인;조광섭
    • 한국진공학회지
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    • 제20권4호
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    • pp.280-287
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    • 2011
  • 열전소자를 사용하여 발광다이오드의 방열효과를 조사하였다. 열전소자의 냉각기능인 펠티에 효과(Peltier effect)를 이용하여, 고전력 발광다이오드의 방열과 p-n접합부의 온도를 제어하였다. 정격전류(350 mA)에 대한 고전력(1 W급) 발광다이오드(Light Emitting Diodes: LEDs)의 온도와 p-n접합부 온도는 각각 $64.5^{\circ}C$$79.1^{\circ}C$이다. 열전소자의 입력 전력 0.1~0.2 W에 대하여, LED의 온도와 접합부 온도는 각각 $54.2^{\circ}C$$68.9^{\circ}C$로 낮아진다. 열전소자에 입력 전력을 0.2 W 이상으로 증가할수록, LED의 온도와 접합부의 온도가 상승한다. 이는 열전소자에 의하여 흡수된 열이 LED로 역류하기 때문이다. 따라서 열전 소자의 냉각기능을 유지하기 위하는 열의 역류를 제어하여야 하며, 열의 역류는 LED의 온도와 방열장치의 온도 차가 클수록 커진다.

SMART-ITL 1 계열 피동안전계통을 이용한 안전주입배관 파단 소형냉각재상실사고 모의에 대한 실험적 연구 (Experimental Study of SBLOCA Simulation of Safety-Injection Line Break with Single Train Passive Safety System of SMART-ITL)

  • 류성욱;배황;유효봉;변선준;김우식;신용철;이성재;박현식
    • 대한기계학회논문집B
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    • 제40권3호
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    • pp.165-172
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    • 2016
  • 노심보충탱크(Core Makeup Tank, CMT), 안전주입탱크(SafetyInjection Tank, SIT)와 자동감압계통(Auto Depressurization System, ADS)로 구성된 1 계열의 SMART 피동안전주입계통의 주입특성을 파악하기 위한 소형냉각재상실사고(SBLOCA) 모의에 대한 실험적 연구가 수행되었다. SBLOCA의시험은 0.4 인치 안전주입수 배관파단에 대해 수행되었으며, 정상상태 조건은 실험요건서에 제시된 시험 초기 조건을 만족시키도록 746초 동안 운전되었다. 노심 출력 및 안전주입 유량 등의 경계 조건도 적절히 모의되었으며, 안전주입계통 배관에서의 파단, 히터 트립 및 잔열곡선 인가, 원자로냉각재펌프 관성서행(Coastdown), 급수 중단, CMT 및 SIT의 주입, ADS #1 개방이 SBLOCA 시나리오에 따라 적절히 모의되었다. 노심지지원통 내부의 액체환산수위는 파단 초반에 감소하다가 CMT와 SIT가 주입되면서 서서히 회복되었으며, 피동안전주입계통의 주입유량이 노심 수위를 회복하기에 충분한 것으로 판단할 수 있다.

MANAGING A PROLONGED STATION BLACKOUT CONDITION IN AHWR BY PASSIVE MEANS

  • Kumar, Mukesh;Nayak, A.K.;Jain, V;Vijayan, P.K.;Vaze, K.K.
    • Nuclear Engineering and Technology
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    • 제45권5호
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    • pp.605-612
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    • 2013
  • Removal of decay heat from an operating reactor during a prolonged station blackout condition is a big concern for reactor designers, especially after the recent Fukushima accident. In the case of a prolonged station blackout condition, heat removal is possible only by passive means since no pumps or active systems are available. Keeping this in mind, the AHWR has been designed with many passive safety features. One of them is a passive means of removing decay heat with the help of Isolation Condensers (ICs) which are submerged in a big water pool called the Gravity Driven Water Pool (GDWP). The ICs have many tubes in which the steam, generated by the reactor core due to the decay heat, flows and condenses by rejecting the heat into the water pool. After condensation, the condensate falls back into the steam drum of the reactor. The GDWP tank holds a large amount of water, about 8000 $m^3$, which is located at a higher elevation than the steam drum of the reactor in order to promote natural circulation. Due to the recent Fukushima type accidents, it has been a concern to understand and evaluate the capability of the ICs to remove decay heat for a prolonged period without escalating fuel sheath temperature. In view of this, an analysis has been performed for decay heat removal characteristics over several days of an AHWR by ICs. The computer code RELAP5/MOD3.2 was used for this purpose. Results indicate that the ICs can remove the decay heat for more than 10 days without causing any bulk boiling in the GDWP. After that, decay heat can be removed for more than 40 days by boiling off the pool inventory. The pressure inside the containment does not exceed the design pressure even after 10 days by condensation of steam generated from the GDWP on the walls of containment and on the Passive Containment Cooling System (PCCS) tubes. If venting is carried out after this period, the decay heat can be removed for more than 50 days without exceeding the design limits.

INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR

  • NAM, SEUNG HYUN;VENNERI, PAOLO;KIM, YONGHEE;LEE, JEONG IK;CHANG, SOON HEUNG;JEONG, YONG HOON
    • Nuclear Engineering and Technology
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    • 제47권6호
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    • pp.678-699
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    • 2015
  • Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for nearterm human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of $100MW_{th}$ and an electricity generation mode of $100MW_{th}$, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and thermohydraulics was carried out. The result indicates that the innovative design has great potential for high propellant efficiency and thrust-to-weight of engine ratio, compared with the existing NTR designs. However, the build-up of fission products in fuel has a significant impact on the bimodal operation of the moderated reactor such as xenon-induced dead time. This issue can be overcome by building in excess reactivity and control margin for the reactor design.

저소음·분진회수형 도로절단기의 친환경성 평가 (Eco-friendliness Evaluation of a Low-Noise and Dust-Recovery Type Pavement Cutter)

  • 김균태
    • Ecology and Resilient Infrastructure
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    • 제8권4호
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    • pp.194-203
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    • 2021
  • 최근에 상하수관로, 지역난방 열공급관로 등의 유지보수가 증가하면서, 도로절단기에 의한 도로절단 작업도 급증하고 있다. 이러한 도로절단 작업은 소음과 함께 분진(절단슬러지)을 많이 발생시키므로, 저소음, 분진회수 등 친환경적인 기술이 적용될 필요가 있다. 기존에 이러한 문제점을 해결하고자 분진을 회수하는 장비가 개발된 사례가 있으나, 친환경성이 정량화되지 않았다는 한계가 있었다. 이에 본 연구에서는 소음 및 분진과 같은 환경위해요인의 발생원인을 근본적으로 제거할 수 있는 저소음·분진회수형 도로절단기를 개발하고, 이 절단기로 수행하는 도로절단작업 과정에 대한 친환경성을 평가하였다. 이를 위하여 본 연구에서는 진공장치와 슬러지흡입부로 구성된 수냉-슬러지회수 통합시스템을 개발하고, 개발된 시스템을 도로절단기에 적용하였다. 그리고 개발된 장비를 테스트 베드에 적용하고, 친환경성 관련 데이터를 수집하여, 친환경성을 평가하였다. 평가 결과, 개발된 장비의 절단슬러지 회수율은 83% 이상이었으며, 소음도는 82~83 dB, 음향파워레벨은 115 dB 수준이었다. 본 연구의 결과는 향후 도로절단기를 개선하는 과정에서 절단슬러지 회수성능과 저소음 성능을 향상시키는 데에 기초자료로 활용될 예정이다.

PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems

  • Michael Montout;Christophe Herer;Joonas Telkka
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.803-811
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    • 2024
  • Nuclear accidents such as Fukushima Daiichi have highlighted the potential of passive safety systems to replace or complement active safety systems as part of the overall prevention and/or mitigation strategies. In addition, passive systems are key features of Small Modular Reactors (SMRs), for which they are becoming almost unavoidable and are part of the basic design of many reactors available in today's nuclear market. Nevertheless, their potential to significantly increase the safety of nuclear power plants still needs to be strengthened, in particular the ability of computer codes to determine their performance and reliability in industrial applications and support the safety demonstration. The PASTELS project (September 2020-February 2024), funded by the European Commission "Euratom H2020" programme, is devoted to the study of passive systems relying on natural circulation. The project focuses on two types, namely the SAfety COndenser (SACO) for the evacuation of the core residual power and the Containment Wall Condenser (CWC) for the reduction of heat and pressure in the containment vessel in case of accident. A specific design for each of these systems is being investigated in the project. Firstly, a straight vertical pool type of SACO has been implemented on the Framatome's PKL loop at Erlangen. It represents a tube bundle type heat exchanger that transfers heat from the secondary circuit to the water pool in which it is immersed by condensing the vapour generated in the steam generator. Secondly, the project relies on the CWC installed on the PASI test loop at LUT University in Finland. This facility reproduces the thermal-hydraulic behaviour of a Passive Containment Cooling System (PCCS) mainly composed of a CWC, a heat exchanger in the containment vessel connected to a water tank at atmospheric pressure outside the vessel which represents the ultimate heat sink. Several activities are carried out within the framework of the project. Different tests are conducted on these integral test facilities to produce new and relevant experimental data allowing to better characterize the physical behaviours and the performances of these systems for various thermo-hydraulic conditions. These test programmes are simulated by different codes acting at different scales, mainly system and CFD codes. New "system/CFD" coupling approaches are also considered to evaluate their potential to benefit both from the accuracy of CFD in regions where local 3D effects are dominant and system codes whose computational speed, robustness and general level of physical validation are particularly appreciated in industrial studies. In parallel, the project includes the study of single and two-phase natural circulation loops through a bibliographical study and the simulations of the PERSEO and HERO-2 experimental facilities. After a synthetic presentation of the project and its objectives, this article provides the reader with findings related to the physical analysis of the test results obtained on the PKL and PASI installations as well an overall evaluation of the capability of the different numerical tools to simulate passive systems.

Research of Diffusion Bonding of Tungsten/Copper and Their Properties under High Heat Flux

  • Li, Jun;Yang, Jianfeng
    • 한국재료학회:학술대회논문집
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    • 한국재료학회 2011년도 춘계학술발표대회
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    • pp.14-14
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    • 2011
  • W (tungsten)-alloys will be the most promising plasma facing armor materials in highly loaded plasma interactive components of the next step fusion reactors due to its high melting point, high sputtering resistance and low deuterium/tritium retention. The bonding technology of tungsten to Cu alloy was one of the key issues. In this paper, W/CuCrZr diffusion bonding has been performed successfully by inserting pure metal interlay. The joint microstructure, interfacial elements migration and phase composition were analyzed by SEM, EDS, XRD, and the joint shear strength and micro-hardness were investigated. The mock-ups were fabricated successfully with diffusion bonding and the cladding technology respectively, and the high heat flux test and thermal fatigue test were carried out under actively cooling condition. When Ni foil was used for the bonding of tungsten to CuCrZr, two reaction layers, Ni4W and Ni(W) layer, appeared between the tungsten and Ni interlayer with the optimized condition. Even though Ni4W is hard and brittle, and the strength of the joint was oppositely increased (217 MPa) due primarily to extremely small thicknesses (2~3 ${\mu}m$). When Ti foil was selected as the interlayer, the Ti foil diffused quickly with Cu and was transformed into liquid phase at $1,000^{\circ}C$. Almost all of the liquid was extruded out of the interface zone under bonding pressure, and an extremely thin residual layer (1~2 ${\mu}m$) of the liquid phase was retained between the tungsten and CuCrZr, which shear strength exceeded 160 MPa. When Ni/Ti/Ni multiple interlayers were used for bonding of tungsten to CuCrZr, a large number of intermetallic compound ($Ni_4W/NiTi_2/NiTi/Ni_3T$) were formed for the interdiffusion among W, Ni and Ti. Therefore, the shear strength of the joint was low and just about 85 MPa. The residual stresses in the clad samples with flat, arc, rectangle and trapezoid interface were estimated by Finite Element Analysis. The simulation results show that the flat clad sample was subjected maximum residual stress at the edge of the interface, which could be cracked at the edge and propagated along the interface. As for the rectangle and trapezoid interface, the residual stresses of the interface were lower than that of the flat interface, and the interface of the arc clad sample have lowest residual stress and all of the residual stress with arc interface were divided into different grooved zones, so the probabilities of cracking and propagation were lower than other interfaces. The residual stresses of the mock-ups under high heat flux of 10 $MW/m^2$ were estimated by Finite Element Analysis. The tungsten of the flat interfaces was subjected to tensile stresses (positive $S_x$), and the CuCrZr was subjected to compressive stresses (negative $S_x$). If the interface have a little microcrack, the tungsten of joint was more liable to propagate than the CuCrZr due to the brittle of the tungsten. However, when the flat interface was substituted by arc interfaces, the periodical residual stresses in the joining region were either released or formed a stress field prohibiting the growth or nucleation of the interfacial cracks. Thermal fatigue tests were performed on the mock-ups of flat and arc interface under the heat flux of 10 $MW/m^2$ with the cooling water velocity of 10 m/s. After thermal cycle experiments, a large number of microcracks appeared at the tungsten substrate due to large radial tensile stress on the flat mock-up. The defects would largely affect the heat transfer capability and the structure reliability of the mock-up. As for the arc mock-up, even though some microcracks were found at the interface of the regions, all microcracks with arc interface were divided into different arc-grooved zones, so the propagation of microcracks is difficult.

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