• Title/Summary/Keyword: Power Circulation

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GEO Satellite Magnetic Momentum Assessment

  • Yang, Jeong-Hwan;Kim, Eui-Chan;Koo, Ja-Chun;Lee, Sang-Kon
    • The Bulletin of The Korean Astronomical Society
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    • v.37 no.2
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    • pp.182.2-182.2
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    • 2012
  • If the satellite has the magnetic material or magnetic moment, the satellite is affected by the earth magnetic field by the space environment in Geostational orbit. The aim of this paper is to assess the satellite magnetic momentum which is an input to ADCS(Altitude Determination Control Subsystem) analyses to assess spurious torques. The magnetic momentum at satellite level is due to magnetic momentum generated by each unit which is due to internal currents circulation or to the presence of magnetic components. Also the magnetic momentum at satellite level is due to circulation of the DC supply current from PSR(Power Supply Regulator) to each unit. As introducing the intrinsic contribution of each unit and the magnetic moment based on the current return through the structure, this paper assess the satellite magnetic moment.

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The Transport of Radionuclides Released From Nuclear Facilities and Nuclear Wastes in the Marine Environment at Oceanic Scales

  • Perianez, Raul
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.3
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    • pp.321-338
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    • 2022
  • The transport of radionuclides at oceanic scales can be assessed using a Lagrangian model. In this review an application of such a model to the Atlantic, Indian and Pacific oceans is described. The transport model, which is fed with water currents provided by global ocean circulation models, includes advection by three-dimensional currents, turbulent mixing, radioactive decay and adsorption/release of radionuclides between water and bed sediments. Adsorption/release processes are described by means of a dynamic model based upon kinetic transfer coefficients. A stochastic method is used to solve turbulent mixing, decay and water/sediment interactions. The main results of these oceanic radionuclide transport studies are summarized in this paper. Particularly, the potential leakage of 137Cs from dumped nuclear wastes in the north Atlantic region was studied. Furthermore, hypothetical accidents, similar in magnitude to the Fukushima accident, were simulated for nuclear power plants located around the Indian Ocean coastlines. Finally, the transport of radionuclides resulting from the release of stored water, which was used to cool reactors after the Fukushima accident, was analyzed in the Pacific Ocean.

A Study on Characteristic Analysis of Auxiliary Power Supply for Railway Vehicle (철도차량 보조전원장치 특성 분석에 관한 연구)

  • Han, Young-Jae;Han, Seong-Ho;Lee, Tae-Young;Lee, Su-Gil;Lee, Young-Ho
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.66 no.4
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    • pp.177-181
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    • 2017
  • Auxiliary power supply for railway vehicle is a equipment that focuses on the service of passengers in a vehicle. It supplies power to controllers used in heating and cooling devices, fluorescent lamps, batteries and many other electrical equipments. Most of the auxiliary power supply for railway vehicle are mainly used for the round trips and circulation routes within the metropolitan area and have a capacity of 170~200 kVA. In this study, we developed the auxiliary power supply capacity to 240kVA for 200km/h class. As such, the auxiliary power supply is an important device for securing the reliability and safety of the railway vehicle and improving the passenger convenience, so the performance verification of the performance must be ensured. In this paper, 240kVA auxiliary power supply is developed. Also, performance of the auxiliary power supply manufactured through the analysis of various characteristics related to the auxiliary power supply was confirmed while operating the actual line.

RCGVS Design Improvement and Depressurization Capability Tests for Ulchin Nuclear Power Plant Units 3 and 4

  • Sung, Kang-Sik;Seong, Ho-Je;Jeong, Won-Sang;Seo, Jong-Tae;Lee, Sang-Keun;Keun hyo Lim;Park, Kwon-Sik;Oh, Chul-Sung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.417-422
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    • 1998
  • he Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3&4(UCN 3&4) has been improved from the Yonggwang Nuclear Power Plant Units 3&4(YGN 3&4) based on the evaluation results for depressurization capability tests performed at YGN 3&4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown Phenomena in order to optimize the orifice size of UCN 3&4 RCGVS. Baesd on these analyses results, the RCGVS orifice size for UCN 3&4 has been reduced to 9/32 inch from the l1/32 inch for YGN 3&4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3&4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation.

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Preliminary conceptual design of a small high-flux multi-purpose LBE cooled fast reactor

  • Xiong, Yangbin;Duan, Chengjie;Zeng, Qin;Ding, Peng;Song, Juqing;Zhou, Junjie;Xu, Jinggang;Yang, Jingchen;Li, Zhifeng
    • Nuclear Engineering and Technology
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    • v.54 no.8
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    • pp.3085-3094
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    • 2022
  • The design concept of a Small High-flux Multipurpose LBE(Lead Bismuth Eutectic) cooled Fast Reactor (SHMLFR) was proposed in the paper. The primary cooling system of the reactor is forced circulation, and the fuel element form is arc-plate loaded high enrichment MOX fuel. The core is cylindrical with a flux trap set in the center of the core, which can be used as an irradiation channel. According to the requirements of the core physical design, a series of physical design criteria and constraints were given, and the steady and transient parameters of the reactor were calculated and analyzed. Regarding the thermal and hydraulic phenomena of the reactor, a simplified model was used to conduct a preliminary analysis of the fuel plates at special positions, and the temperature field distribution of the fuel plate with the highest power density under different coolant flow rates was simulated. The results show that the various parameters of SHMLFR meet the requirements and design criteria of the physical design of the core and the thermal design of the reactor. This implies that the conceptual design of SHMLFR is feasible.

Modeling of Solid Circulation in a Fluidized-Bed Dry Absorption and Regeneration System for CO2 Removal from Flue Gas (연소기체로부터 CO2 회수를 위한 건식 유동층 흡수-재생 공정의 고체순환 모사)

  • Choi, Jeong-Hoo;Park, Ji-Yong;Yi, Chang-Keun;Jo, Sung-Ho;Son, Jae-Ek;Ryu, Chong Kul;Kim, Sang-Done
    • Korean Chemical Engineering Research
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    • v.43 no.2
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    • pp.286-293
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    • 2005
  • An interpretation on the solid circulation characteristics in a fluidized-bed process has been carried out as a first step to simulate the dry entrained-bed absorption and bubbling-bed regeneration system for $CO_2$ removal from flue gas. A particle population balance has been developed to determine the solid flow rates and particle size distributions in the process. Effects of principal process parameters have been discussed in a laboratory scale process (absorption column: 25 mm i.d., 6 m in height; regeneration column: 0.1 m i.d., 1.2 m in height). The particle size distributions in absorption and regeneration columns were nearly the same. As gas velocity or static bed height in the absorption column increased, soild circulation rate and feed rate of fresh sorbent increased, however, mean particle diameter decreased in the absorption column. As cut diameter of the cyclone of the absorption column increased, solid circulation rate decreased, whereas feed rate of fresh sorbent and mean particle diameter in the absorption column increased. As attrition coefficient of sorbent particle increased, solid circulation rate and feed rate of fresh sorbent increased but mean particle diameter in the absorption column decreased.

Field Applications of Non-powered Downward Water Circulation System to Improve Reservoir Water Quality (저수지 수질개선을 위한 무동력 하향류 수류순환시스템의 현장적용성)

  • Jang, YeoJu;Lim, HyunMan;Jung, JinHong;Park, JaeRho;Kim, WeonJae
    • Ecology and Resilient Infrastructure
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    • v.6 no.2
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    • pp.109-119
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    • 2019
  • Eutrophication has occurred due to the inflow of various water pollutants in many Korean reservoirs with low depth, and algal blooms of surface layer and low oxygenation of deep layer have repeated every year. There are several existing technologies to alleviate the stratification of reservoirs, but it is difficult to apply them in field sites due to the necessity of electric power and low economic efficiency. In this study, a non-powered water circulation system using natural energy of wind and water flow has been developed, and two test-beds constructed in the reservoirs with different conditions and examined its field applicability. Through computational fluid dynamics (CFD) simulation, it has been shown that the water circulation system could induce the downward flow to mitigate the stratification between surface and deep layers, and its influence radius could reach about 30 m. As a result of long-term monitoring of the test-beds, various water quality improvement effects have been observed such as moderation of DO fluctuation by water circulation, reduction of DO supersaturation and prevention of excessive pH rising. In order to improve the applicability of the water circulation system, it is considered necessary to review countermeasures against flood and depth conditions of each reservoir.

Power Flow Analysis for Manufacturing of Planetary Gears in a 8-Speed Automatic Transmission (I): 1-3 Speeds (8단 자동변속기의 유성기어 가공을 위한 동력 흐름 해석 (I) : 1-3단)

  • Lee, Kyoung-Jin;Kim, Jeong-Min
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.15 no.5
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    • pp.48-56
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    • 2016
  • In this paper, we analyze the power flow of an eight-speed automatic transmission by using a lever analogy for the manufacturing of planetary gears. The results indicate that the engine power is passed down to the carrier and ring gear in the first double pinion planetary gear (DPPG1), and to the sun gear, carrier, and ring gear in DPPG3 for the first speed. Although the power flow is similar in the second speed, the power circulation occurs in the second single pinion planetary gear (SPPG2). For the third speed, the engine power is passed from the carrier to the ring gear in DPPG, at which point the power is split between the sun gears of SPPG2 and DPPG3.

Numerical Investigation on Experiment for Passive Containment Cooling System (피동 원자로건물 냉각계통 실험에 관한 수치적 연구)

  • Ha, Hui Un;Suh, Jung Soo
    • Journal of the Korean Society of Safety
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    • v.35 no.3
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    • pp.96-104
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    • 2020
  • The numerical simulations were conducted to investigate the thermal-fluid phenomena occurred inside the experimental apparatus during a PCCS, used to remove heat released in accidents from a containment of light water nuclear power plant, operation. Numerical simulations of the flow and heat transfer caused by wall condensation inside the containment simulation vessel (CSV), which equipped with 18 vertical heat exchanger tubes, were conducted using the commercial computational fluid dynamics (CFD) software ANSYS-CFX. Shear stress transport (SST) and the wall condensation model were used for turbulence closure and wall condensation, respectively. The simulation using the actual size of the apparatus. However, rather than simulating the whole experimental apparatus in consideration of the experimental cases, calculation resources, and calculation time, the simulation model was prepared only in CSV. Selective simulation was conducted to verify the effects of non-condensable gas(NC gas) concentration, CSV internal pressure, and wall sub-cooling conditions. First, as a result of the internal flow of CSV, it was observed that downward flow due to condensation occurred surface of the vertical tube and upward flow occurred in the distant place. Natural convection occurred actively around the heat exchanger tube. Due to this rising and falling internal flow, natural circulation occurred actively around the heat exchanger tubes. Next, in order to check the performance of built-in condensation model using according to the non-condensable gas concentration, CSV internal flow and wall sub-cooling, the heat flux values were compared with the experimental results. On average, the results were underestimated with and error of about 25%. In addition, the influence of CSV internal pressure and wall sub-cooling was small, but when the condensate was highly generated due to the low non-condensable gas concentration, the error was large compared to the experimental values. This is considered to be due to the nature of the condensation model of the CFX code. However, in spite of the limitations of CFD, it is valid to use the built-in condensation model of CFD for PCCS performance prediction from a conservative perspective.

Performance Test of Cooling System for the KEPCO HTS Power Cable (한전 초전도전력케이블 냉각시스템 성능시험)

  • Yang, H.S.;Kim, D.L.;Sohn, S.H.;Lim, J.H.;Choi, H.O.;Lee, B.S.;Choi, Y.S.;Ryoo, H.S.;Hwang, S.D.
    • Proceedings of the KSME Conference
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    • 2007.05b
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    • pp.2206-2210
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    • 2007
  • As a power transmission line supplying power to a densely populated city, the high temperature superconducting (HTS) cable is expected to one of the most effective cables with a compact size because of its high current density. The verification of HTS power cable system have been progressed by KEPRI. A cooling system for a 3-phase 100m HTS power cable with 22.9kV/1.25kA was installed and tested at KEPCO's Gochang power testing center in Korea. The system consists of a liquid nitrogen decompression cooling system with a cooling capacity of 3kW and a closed circulation system of subcooled liquid nitrogen. Several performance tests of the cable system with respect to the cooling such as cooling capacity, heat load and temperature stability, were performed at several temperatures. Thermal cycle test, cool-down to liquid nitrogen temperature and warm-up to room temperature, was also performed to investigate thermal cycle influences. The outline of the installed cooling system and performance test results are presented in this paper.

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