3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors - Couverture souple

Pandey, Krishna; Sharma, Deepak

9783659462887: 3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors

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ISBN 10 : 3659462888 ISBN 13 : 9783659462887

Editeur : LAP LAMBERT Academic Publishing, 2013

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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 40�C. 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.

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� propos de l?auteur

Dr.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 in National & International Conferences & International Journals. Currently he is working as professor in NIT Silchar Assam, India.

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�diteurLAP LAMBERT Academic Publishing
Date d'�dition2013
ISBN 10 3659462888
ISBN 13 9783659462887
ReliureBroch�
Langueanglais
Nombre de pages92
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3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors

Krishna Pandey|Deepak Sharma

Edit� par LAP LAMBERT Academic Publishing, 2013

ISBN 10 : 3659462888 ISBN 13 : 9783659462887

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Etat : 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 . N� de r�f. du vendeur 5157610

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3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors

Krishna Pandey

Edit� par LAP LAMBERT Academic Publishing Sep 2013, 2013

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Taschenbuch. Etat : 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 40�C. 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. N� de r�f. du vendeur 9783659462887

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3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors

Krishna Pandey

Edit� par LAP LAMBERT Academic Publishing Sep 2013, 2013

ISBN 10 : 3659462888 ISBN 13 : 9783659462887

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Vendeur : buchversandmimpf2000, Emtmannsberg, BAYE, Allemagne

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Taschenbuch. Etat : Neu. 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 40�C. 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.Books on Demand GmbH, �berseering 33, 22297 Hamburg 92 pp. Englisch. N� de r�f. du vendeur 9783659462887

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3D CFD Analysis of Heat Transfer in Sub Channels of Nuclear Reactors

Krishna Pandey

Edit� par LAP LAMBERT Academic Publishing, 2013

ISBN 10 : 3659462888 ISBN 13 : 9783659462887

Neuf Taschenbuch

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Vendeur : AHA-BUCH GmbH, Einbeck, Allemagne

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Taschenbuch. Etat : 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 40�C. 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. N� de r�f. du vendeur 9783659462887

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