Fluid Axial Conduction Effect: Liquid Metal Natural Circulation - Couverture souple

Sabharwall, Piyush

 
9783639195569: Fluid Axial Conduction Effect: Liquid Metal Natural Circulation
Couverture souple
ISBN 10 : 3639195566 ISBN 13 : 9783639195569
Editeur : VDM Verlag, 2009

Synopsis

Stability analysis was performed for Secure Transportable Autonomous Reactor ? Liquid Metal (STAR-LM) fast reactor which included the effects of axial thermal conduction through lead bismuth eutectic (LBE) along its direction of flow. The results suggested that fluid axial heat conduction in natural circulation loop should be considered only when the modified Peclet number is in the order of one or below, which is significantly smaller than the practical value (100,000 in the specified loop) of liquid metal natural circulation systems. Therefore, it is appropriate to neglect fluid axial heat conduction effect in the thermal hydraulics analysis related to liquid metal natural circulation cooled nuclear reactors. However, at low heating power conditions, as in the case of reactor start-up or long term cooling after shutdown, fluid axial thermal conduction could become important because of the slow coolant natural circulation. In those cases, the magnitude of the system Peclet number should be closely examined to validate the neglecting of fluid axial heat conduction in natural circulation analysis.

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Présentation de l'éditeur

Stability analysis was performed for Secure Transportable Autonomous Reactor ? Liquid Metal (STAR-LM) fast reactor which included the effects of axial thermal conduction through lead bismuth eutectic (LBE) along its direction of flow. The results suggested that fluid axial heat conduction in natural circulation loop should be considered only when the modified Peclet number is in the order of one or below, which is significantly smaller than the practical value (100,000 in the specified loop) of liquid metal natural circulation systems. Therefore, it is appropriate to neglect fluid axial heat conduction effect in the thermal hydraulics analysis related to liquid metal natural circulation cooled nuclear reactors. However, at low heating power conditions, as in the case of reactor start-up or long term cooling after shutdown, fluid axial thermal conduction could become important because of the slow coolant natural circulation. In those cases, the magnitude of the system Peclet number should be closely examined to validate the neglecting of fluid axial heat conduction in natural circulation analysis.

Biographie de l'auteur

Dr.Sabharwall is the heat transport lead for NGNP division at Idaho National Lab. Dr. Wu is an Associate Professor in the Department of Nuclear Engineering and Radiation Health Physics at Oregon State University. Their Research interests:thermal hydraulics, reactor safety, reactor engineering & design, multi-phase flow & boiling heat transfer.

Les informations fournies dans la section « A propos du livre » peuvent faire référence à une autre édition de ce titre.

Éditeur
VDM Verlag
Date d'édition
2009
Langue
anglais
ISBN 10 
3639195566
ISBN 13 
9783639195569
Reliure
Broché
Nombre de pages
92
Coordonnées du fabricant
non disponible
Personne responsable
non disponible