An assessment methodology for in-vessel cerium retention by external reactor vessel cooling during severe accidents in PWRs

A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten cerium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs). By combining the results of Level-1 probabilistic safety assessment, a critical heat flux correlation, and wall heat flux distributions calculated by a severe accident code with appropriate adjustment, we can reasonably predict the overall success probability of the IVR-ERVC from the viewpoint of thermal failure. The practicability of the proposed approach is illustrated with a preliminary application to the Korean Standard Nuclear Power Plant. This paper also discusses future developmental needs for more reliable assessment. (C) 2001 Elsevier Science Ltd. All rights reserved.
Publisher
Pergamon-Elsevier Science Ltd
Issue Date
2001-08
Language
ENG
Keywords

COOLABILITY; PRESSURE

Citation

ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250

ISSN
0306-4549
URI
http://hdl.handle.net/10203/1890
Appears in Collection
NE-Journal Papers(저널논문)
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