• Title/Summary/Keyword: Loop-pipe

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THE ANALYTIC ANALYSIS OF THE CORE INJECTION COOLING FLOW RATE FOR EMERGENCY WATER SUPPLY SYSTEM IN HANARO (하나로 비상 보충수 공급계통의 노심 주입 냉각유량 해석)

  • Park Yong-Chul;Kim Bong-Soo;Kim Kyung-Ryun;Wu Jong-Sub
    • 한국전산유체공학회:학술대회논문집
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    • 2005.10a
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    • pp.39-44
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    • 2005
  • In HANARO, a multi-purpose research reactor of 30 MWth, the emergency water supply system consists essentially of an emergency water storage tank located in the level of about thirteen meter (13 m) above the reactor core, a three inch ('3\%') diameter water injection pipe line including injection valves from the tank to the reactor cooling inlet pipe and a test loop to do periodic system performance test. When the water level of the reactor pool comes down to the extremely low due to a loss of reactor pool water accident the emergency water stored in the tank should be fed to the core by the gravity force and at that time the design flow rate is eleven point four kilogram per second (11.4 kg/s). But it is impossible periodically to measure the injection flow rate under the emergency condition because the normal water level should be maintained during the reactor operation. This paper describes a flow network analysis to simulate the flow rate under the emergency condition. As results, it was confirmed through the analysis results that the calculated flow rate agrees with the design requirement under the emergency condition.

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Hydraulic Tests of Fuel Pump for 75-ton class Liquid Rocket Engines (75톤급 로켓엔진용 연료펌프의 수력성능시험)

  • Kim, Dae-Jin;Hong, Soon-Sam;Choi, Chang-Ho;Noh, Jun-Gu;Kim, Jin-Han
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2009.11a
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    • pp.78-81
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    • 2009
  • A series of hydraulic tests of a fuel pump are performed using water at a room temperature. The pump is under development for 75-ton class liquid rocket engines of the open-loop gas generator type. According to the test results, the fuel pump satisfies its design requirement and its head and efficiency at the design flowrate are higher than the expected value by the computational analysis. Also, it is found that the pressure at the rear bearing outlet is higher than expected because the inlet of bypass pipe line is narrow. Furthermore, the flowrate of the secondary flow is estimated using the pressure difference of the elbow of the bypass pipe line.

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The Characteristics of Thermal Diffusion With the Vertical-Closed Loop Type Geothermal Heat Exchanger (수직밀폐형 지중열교환기의 온도분포 특성)

  • Sun, Jong-Cheol;Kim, Byung-Chul;Koh, Young-Ha
    • Journal of the Korean Solar Energy Society
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    • v.33 no.1
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    • pp.57-65
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    • 2013
  • The temperatures with the ground depth, the positions of circulation water in ground heat exchanger were measured and thermal diffusion characteristics with the distances of the direction normal to the borehole was analysed. The deeper the depth of ground, the less the influences of outdoor temperature, but below 10m of ground, there was no influences of ground temperature. When the depth of trench pipe was below the depth of 2m, there was no influence. In the ground of 10m when the distances between the pipe and the other places were above 0.5m, the variations of temperature were less than $1.6^{\circ}C$ and above 2.5m they were less than $0.1^{\circ}C$. When the distances of bore hole were above 5m, there were no. influences of the nearest ground heat exchanger.

Numerical Simulation on the Heat Transfer Characteristics of a Solar Thermal Receiver Depending on the End-Wall Angle Variation (고온 태양열 흡수기의 후벽 각도 변화에 따른 열전달 특성에 관한 수치적 모사)

  • Jung, Eui-Guk;Boo, Joon-Hong;Kang, Yong-Hyeog
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.2100-2105
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    • 2008
  • A numerical analysis was conducted to predict the heat transfer characteristics of a high-temperature, high heat flux solar receiver as the end-wall angle varied. The concentration ratio of the solar receiver ranges from 200 to 1000 and the concentrated heat is required to be transported to a certain distance for specific applications. This study deals with a solar receiver incorporating high-temperature sodium heat pipe as well as a typical one that employs a molten-salt circulation loop with the same outer dimensions. The isothermal characteristics in the receiver section is of major concern. The diameter of the solar thermal receiver was 120 mm and the length was 400 mm. FLUENT, a commercial software, was employed to deal with the radiative heat transfer inside the receiver cavity and the convection heat transfer along the channels and heat pipes. The numerical results were compared and analyzed from the view point of heat transfer characteristics the solar receiver system.

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The Effects of Copolymer Additives for Drag Reduction on Turbulent Flow (합성고분자첨가제의 난류마찰저항 감소효과 연구)

  • Kim, N.S.;Kim, C.B.;Kim, I.S.;Choi, H.J.
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.5 no.3
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    • pp.207-216
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    • 1993
  • Experimental investigations have been carried out to find the effect of drag reduction caused by effective polymer additives in turbulent flows. The experiments were undertaken with a test section of 9.8mm pipe diameter and 3500 mm pipe length(L/D=357) in a closed loop, and Copolymer-X and Polyacrylamide(PAAM) were used as polymer additives for comparisons. The tests were carried out under different polymer concentrations, and the temperatures of the flow considered were $26^{\circ}C$, $60^{\circ}C$ at the flow velocity of 5.3 m/s. The rate of drag reduction obtained by Copolymer-X is found to be considerably higher than that of PAAM in turbulent flows. Copolymer-X is also found to be very reliable for mechanical degradation, which has not been the case in any other additives. It is concluded that Copolymer-X is considered to be one of the most effective agents as an additive especially for long time hydraulic transports. It is also found that polymer degradation in more likely at lower polymer concentrations in the turbulent flows.

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Study on the Design and the Prototype Manufacture of Cooling systems of the Propulsion System for the EMU (동력분산형 고속전철의 추진시스템용 냉각장치 설계 및 시제품 제작 연구)

  • Ryoo, Seong-Ryoul;Kim, Sung-Dae;Ki, Jae-Hyung;Yim, Kwang-Bin;Kim, Chul-Ju
    • Proceedings of the KSR Conference
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    • 2008.11b
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    • pp.422-429
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    • 2008
  • The objective of the present study is to develope a propultion unit cooling system for the next-generation High-speed EMU. The propulsion power control unit consists of some IGBT semiconductors. In general, those power semiconductors are very sensitive to temperatures and need a cooling system to keep them at a proper operational conditions in the range of $50{\sim}100^{\circ}C$. In this first year of study, we tried to focuss on the understanding of fundamental technologies for each of the two different cooling systems and collecting basic data for design and manufacturing for both cases. For the water cooling system, a heat sink with multi channels of liquid flow was considered and a model unit was designed and performance test was conducted. For the heat pipe cooling system, a Loop Heat Pipe(LHP) was considered as an element to transport heat from IGBT to environment air flow and a model unit was designed and performance test was conducted. The analysis using SINDA/FLUINT showed that those design parameters are good enough for the LHP to properly operate under a heat load up to around 360W.

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Design of Vessel Assembly for Fuel Irradiation Test in Reactor (원자로 내 핵연료조사시험용 압력용기조립체 설계)

  • Park, Kook-Nam;Lee, Jong-Min;Chi, Dae-Young;Park, Su-Ki;Lee, Chung-Young;Kim, Young-Jin
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.383-387
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    • 2004
  • The Fuel Test Loop (FTL) consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). The test condition in IPS such as pressure, temperature and quality of the main cooling water, can be controlled by the OPS. The FTL has been developed to be able to irradiate three pins to the core irradiation hole (IR1 hole) by considering for its utility and user's irradiation requirement. The IPS vessel assembly (IVA) consists of IPS head, outer pressure vessel, inner pressure vessel, inner assembly and test fuel carrier. The IVA is approximately 5.6 m long and fits within a 74 mm in diameter envelope over the full height of the chimney. Above the top of the chimney, the head of the IPS is enlarged to allow the closure flanges and pipe work connections. IVA was designed to test the CANDU and PWR nuclear fuel pin together. Specially, wished to minimize interference by nuclear fuel change in design and synthesize these items and shape design for IVA.

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Pressure Drop Characteristics of Supercritical $CO_2$ in a Helically Coiled Tube (헬리컬 코일관 내 초임계 $CO_2$의 압력강하 특성)

  • Yu, Tae-Geun;Kim, Dae-Hui;Roh, Geon-Sang;Ku, Hak-Geun;Oh, Hoo-Kyu
    • Proceedings of the Korean Society of Marine Engineers Conference
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    • 2005.06a
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    • pp.216-221
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    • 2005
  • The heat transfer coefficient and pressure drop during gas cooling process of carbon dioxide in a helically coiled tube were investigated experimentally. The experiments were conducted without oil in the refrigerant loop. The main components of the refrigerant loop are a receiver, a variable speed pump, a mass flowmeter, a pre-heater, a gas cooler(test section) and an isothermal tank. The test section is a double pipe type heat exchanger with refrigerant flowing in the inner tube and water flowing in the annulus. It was made of a copper tube with the inner diameter of 4.85 [mm], the outer diameter of 6.35 [mm] and length of 10000 [mm]. The refrigerant mass fluxes were 200${\sim}$600 [kg/$m^2$s] and the average pressure varied from 7.5 [MPa] to 10.0 [MPa]. The main results were summarized as follows: The heat transfer coefficient of supercritical $CO_2$ increases, as the cooling pressure of gas cooler decreases. And the heat transfer coefficient increases with the increase of the refrigerant mass flux. The pressure drop decreases in increase of the gas cooler pressure and increases with increase the refrigerant mass flux.

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A Study on the Free Surface Vortex in the Pipe System (배관내 자유수면에서 와류현상에 대한 연구)

  • Kim, Sang-Nyung;Jang, Wan-Ho
    • Nuclear Engineering and Technology
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    • v.24 no.3
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    • pp.311-318
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    • 1992
  • During mid-loop operation of Nuclear Power Plant, to prevent the Decay Heat Removal System (DHRS) from failure due to air entrainment of free surface vortex in the piping system, a set of simulating experiments was performed. Through these experiments, a relation between the non-dimensionalized numbers, such as H/d, Froude number, Reynolds number, was found. It was also found that the perturbation of the system by the disturbance such as pump start, valve operation, etc., has a strong effect on the free surface vortex. Furthermore, from viewpoint of reactor safety, a modified inlet device which is reducer type is strongly recommended for the prevention of air entrainment into DHRS.

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Study on the Optimum Design of Ground Source Heat Pumps (지열원 히트펌프 시스템의 최적 설계 기법 연구)

  • Choi, Jong Min
    • Journal of the Korean Society for Geothermal and Hydrothermal Energy
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    • v.14 no.4
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    • pp.35-42
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    • 2018
  • Among the various ground source heat pump systems, vertical-type heat pump systems have been distributed greatly. Most of the vertical-type ground source heat pump systems have been designed based on the Korean Ministry of Knowledge Economy Announcement in Korea. In this study, the design process of the vertical-type ground source heat pump system in the announcement was analyzed, and the effects of the design parameters on the ground loop heat exchanger were investigated. Borehole thermal conductivity was the highest dominant design parameter for ground loop heat exchangers. The borehole thermal conductivity was changed according to the pipe and grout thermal conductivity. For optimal design of the ground heat pump system, it is highly recommended that the design process in the announcement will be revised to adopt the various tubes and grout which have higher thermal conductivity. In addition, the certification standard for heat pump unit should be revised to develop the heat pump with a small flow rate.