Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs
Author:
Affiliation:
1. Division of Engineering Sciences, Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094, India; Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085, India
Abstract
Publisher
ASME International
Subject
Nuclear Energy and Engineering,Radiation
Link
http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4044410/6510011/ners_006_03_031301.pdf
Reference13 articles.
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3. SULTAN Test Facility for Large-Scale Vessel Cool Ability in Natural Convection at Low Pressure;Nucl. Eng. Des.,1997
4. Critical Heat Flux Experiments on the Reactor Vessel Wall Using 2-D Slice Test Section;Nucl. Technol.,2005
5. A Hydrodynamic Critical Heat Flux Model for Saturated Pool Boiling on a Downward Facing Curved Heating Surface;Int. J. Heat Mass Transfer,1997
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