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PWR core response for a steamline break accident-sensitivity studies

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6877317
 [1]; ; ;
  1. Nuclear Associates International Corp., Rockville, MD
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None
OSTI ID:
6877317
Report Number(s):
CONF-800607-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
Country of Publication:
United States
Language:
English

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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
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POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STEAM LINES
WATER COOLED REACTORS
WATER MODERATED REACTORS