Author:
Talley Darren G.,Shen Yu-Lin
Subject
Nuclear Energy and Engineering
Reference24 articles.
1. Critical heat flux in TRIGA-fueled reactors cooled by natural convection;Avery;Nucl. Sci. Eng.,2012
2. The determination of forced-convection surface-boiling heat transfer;Bergles;J. Heat Transfer,1964
3. Department of Energy (DOE), 2014. Preparation of Nonreactor Nuclear Facility Documented Safety Analysis, DOE-STD-3009-2014. Washington D.C.
4. Nuclear Reactor Analysis;Duderstadt,1976
5. Overview of accident analysis in research reactors;Hamidouche;Prog. Nucl. Energy,2008
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