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Volumn 190, Issue , 1991, Pages 63-78
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Thermal-hydraulic correlations for the advanced neutron source reactor fuel element design and analysis
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Author keywords
[No Author keywords available]
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Indexed keywords
FLOW OF FLUIDS;
HEAT TRANSFER - CONVECTION;
NEUTRONS - SOURCES;
NUCLEAR FUELS - DESIGN;
ADVANCED NEUTRON SOURCE;
CRITICAL HEAT FLUX;
THERMAL HYDRAULICS;
NUCLEAR FUELS;
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EID: 0026378264
PISSN: 02725673
EISSN: None
Source Type: Conference Proceeding
DOI: None Document Type: Conference Paper |
Times cited : (4)
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References (100)
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