TY - GEN
T1 - Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System
AU - Cheung, F. B.
AU - Yang, J.
AU - Dizon, M. B.
AU - Rempe, J. L.
AU - Suh, K. Y.
AU - Kim, S. B.
N1 - Copyright:
Copyright 2020 Elsevier B.V., All rights reserved.
PY - 2003
Y1 - 2003
N2 - As part of joint U.S.-Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to enhance external cooling of advanced reactor vessel under severe accident conditions, a scaling analysis has been performed to study the phenomena of external cooling of an advanced reactor vessel under severe accident conditions. Five key transfer processes have been considered and the characteristic time for each of these processes has been determined and compared with the residence time for external reactor vessel cooling (ERVC) in the flow channel. To complement the scaling analysis, an ERVC upward co-current two-phase flow model has been developed to predict the total mass flow rate induced in the annular channel by the process of downward facing boiling on the vessel outer surface. The model takes into account the wall heat flux level, the geometry of the vessel/insulation system, the local variation of the cross-sectional flow area, and the pressure drops through various segments of the channel. Based on the results of the ERVC flow calculations and the scaling analysis, criteria for experimental simulation have been established to assure that the ERVC phenomena simulated in laboratory-scale experiments would have the same effects as those anticipated for the full-scale reactor system.
AB - As part of joint U.S.-Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to enhance external cooling of advanced reactor vessel under severe accident conditions, a scaling analysis has been performed to study the phenomena of external cooling of an advanced reactor vessel under severe accident conditions. Five key transfer processes have been considered and the characteristic time for each of these processes has been determined and compared with the residence time for external reactor vessel cooling (ERVC) in the flow channel. To complement the scaling analysis, an ERVC upward co-current two-phase flow model has been developed to predict the total mass flow rate induced in the annular channel by the process of downward facing boiling on the vessel outer surface. The model takes into account the wall heat flux level, the geometry of the vessel/insulation system, the local variation of the cross-sectional flow area, and the pressure drops through various segments of the channel. Based on the results of the ERVC flow calculations and the scaling analysis, criteria for experimental simulation have been established to assure that the ERVC phenomena simulated in laboratory-scale experiments would have the same effects as those anticipated for the full-scale reactor system.
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U2 - 10.1115/ht2003-47208
DO - 10.1115/ht2003-47208
M3 - Conference contribution
AN - SCOPUS:1842678313
SN - 0791836940
SN - 9780791836941
T3 - Proceedings of the ASME Summer Heat Transfer Conference
SP - 393
EP - 401
BT - Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2
PB - American Society of Mechanical Engineers
T2 - 2003 ASME Summer Heat Transfer Conference (HT2003)
Y2 - 21 July 2003 through 23 July 2003
ER -