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SAS3D analysis of natural-convection boiling behavior in the sodium boiling test facility

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5351438
 [1];
  1. Oak Ridge National Lab., TN
+ Show Author Affiliations
None
OSTI ID:
5351438
Report Number(s):
CONF-791103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BOILING
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MECHANICS
NATURAL CONVECTION
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST FACILITIES
TEST REACTORS