ISBN: 9783659462887 - 3d cfd analysis of heat transfer in sub channels of nuclear reactors (11 risultati)

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Paperback. Condizione: Brand New. 92 pages. 8.66x5.91x0.21 inches. In Stock.

Paperback. Condizione: Brand New. 92 pages. 8.66x5.91x0.21 inches. In Stock.

Taschenbuch. Condizione: Neu. 3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors | Krishna Pandey (u. a.) | Taschenbuch | 92 S. | Englisch | 2013 | LAP LAMBERT Academic Publishing | EAN 9783659462887 | Verantwortliche Person für die EU: preigu GmbH & Co. KG, Lengericher Landstr. 19, 49078 Osnabrück, mail[at]preigu[dot]de | Anbieter: preigu. …

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Taschenbuch. Condizione: Neu. This item is printed on demand - it takes 3-4 days longer - Neuware -In this research project a method has been analysed through CFD technique to obtain steady state heat transfer in nuclear fuel rod assembly and the local heat transfer coefficients of carbon dioxide at supercritical pressures in triangular channel under cooling conditions is presented through the numerical simulation. The CFD code Ansys CFX has been used to simulate the convective heat transfer coefficient of the triangular channel. Supercritical CO2 heat-transfer data were obtained at reactor-equivalent conditions at three pressures above the critical point (7.6, 8.4 and 8.8 MPa), mass fluxes from 840 to 3000 kg/m2s,heat fluxes up to 600 kW/m2 and inlet temperatures from 20 to 40ºC. The effects of pressure, mass flux of supercritical CO2, rod diameter, and heat flux on heat transfer are investigated. The computational results showed that the sharply varying thermo physical properties of carbon dioxide have a significant role on the local heat transfer coefficient which varies significantly along the triangular channel and small tube when the CO2 bulk temperatures were within the near-critical region. 92 pp. Englisch.…

Taschenbuch. Condizione: Neu. nach der Bestellung gedruckt Neuware - Printed after ordering - In this research project a method has been analysed through CFD technique to obtain steady state heat transfer in nuclear fuel rod assembly and the local heat transfer coefficients of carbon dioxide at supercritical pressures in triangular channel under cooling conditions is presented through the numerical simulation. The CFD code Ansys CFX has been used to simulate the convective heat transfer coefficient of the triangular channel. Supercritical CO2 heat-transfer data were obtained at reactor-equivalent conditions at three pressures above the critical point (7.6, 8.4 and 8.8 MPa), mass fluxes from 840 to 3000 kg/m2s,heat fluxes up to 600 kW/m2 and inlet temperatures from 20 to 40ºC. The effects of pressure, mass flux of supercritical CO2, rod diameter, and heat flux on heat transfer are investigated. The computational results showed that the sharply varying thermo physical properties of carbon dioxide have a significant role on the local heat transfer coefficient which varies significantly along the triangular channel and small tube when the CO2 bulk temperatures were within the near-critical region.…

Condizione: New. Dieser Artikel ist ein Print on Demand Artikel und wird nach Ihrer Bestellung fuer Sie gedruckt. Autor/Autorin: Pandey KrishnaDr.K.M Pandey did B.Tech in Mechanical Engineering in 1980 from BHUIT, Varanasi,India. He obtained M.Tech in Heat Power in 1987. He received Ph.D in 1994 from IIT Kanpur, India. He has got more than 300 research papers .…

Condizione: New. Print on Demand.

Condizione: New. PRINT ON DEMAND.

Taschenbuch. Condizione: Neu. This item is printed on demand - Print on Demand Titel. Neuware -In this research project a method has been analysed through CFD technique to obtain steady state heat transfer in nuclear fuel rod assembly and the local heat transfer coefficients of carbon dioxide at supercritical pressures in triangular channel under cooling conditions is presented through the numerical simulation. The CFD code Ansys CFX has been used to simulate the convective heat transfer coefficient of the triangular channel. Supercritical CO2 heat-transfer data were obtained at reactor-equivalent conditions at three pressures above the critical point (7.6, 8.4 and 8.8 MPa), mass fluxes from 840 to 3000 kg/m2s,heat fluxes up to 600 kW/m2 and inlet temperatures from 20 to 40ºC. The effects of pressure, mass flux of supercritical CO2, rod diameter, and heat flux on heat transfer are investigated. The computational results showed that the sharply varying thermo physical properties of carbon dioxide have a significant role on the local heat transfer coefficient which varies significantly along the triangular channel and small tube when the CO2 bulk temperatures were within the near-critical region.VDM Verlag, Dudweiler Landstraße 99, 66123 Saarbrücken 92 pp. Englisch.…