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Transient heat transfer and fluid mechanics of a recirculating pressurized water loop during blowdown and cold water injection
Author(s) -
Barclay F. W.,
Nieman R. E.,
Hasinoff M. P.
Publication year - 1981
Publication title -
the canadian journal of chemical engineering
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.404
H-Index - 67
eISSN - 1939-019X
pISSN - 0008-4034
DOI - 10.1002/cjce.5450590211
Subject(s) - boiler blowdown , heat transfer , fluid mechanics , transient (computer programming) , mechanics , pressurized water reactor , nuclear engineering , fluid dynamics , loop (graph theory) , thermal hydraulics , hydraulics , thermodynamics , engineering , computer science , mechanical engineering , physics , mathematics , inlet , operating system , combinatorics
Mathematical models, in the form of computer codes, are used to evaluate the performance of process and safety systems of CANDU nuclear reactors during normal operation and postulated accident conditions. To validate the models, predictions are made of the transient heat transfer and fluid mechanics processes in pressurized water loops following simulated pipe ruptures. These loops have the essential geometric and physical characteristics of a CANDU reactor primary heat transport system. Comparisons with data from loops of different scales over the conditions of interest (blowdown and cold water injection) are used to illustrate that the models predict the trends in the experiments adequately when the assumptions inherent in the model (e. g. equal steam and water velocities) are valid. To improve accuracy in cases where these assumptions do not apply, a more sophisticated representation of two‐phase flow is required.