A Phenomenological Model for Prediction of Critical Heat Flux under Highly Subcooled Conditions
Author:
Affiliation:
1. University of Cincinnati, Nuclear Engineering Program, Cincinnati, Ohio 45221
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST88-A25140
Reference9 articles.
1. Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part I. A Review of Fundamentals of CHF and Related Data Base
2. Prediction of critical heat flux in flow boiling at low qualities
3. Prediction of the critical heat flux in flow boiling at intermediate qualities
4. R. T. LAHEY and F. MOODY, The Thermal Hydraulics of a Boiling Water Reactor, p. 214, American Nuclear Society, La Grange Park, Illinois (1977).
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