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PWR core thermal-hydraulic response during steam line break accident

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5899074
 [1]; ; ;
  1. Nucleus Associates Internaional Corp., Rockeville, MD
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None
OSTI ID:
5899074
Report Number(s):
CONF-790602-(Summ.)
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
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Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STEAM LINES
STEAM SYSTEMS
WATER COOLED REACTORS
WATER MODERATED REACTORS