학술논문

Results of the first nuclear-powered loss-of-coolant experiments in the LOFT Facility
Document Type
Journal Article
Author
Source
Nucl. Saf.; (United States); 21:4
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS LOSS OF COOLANT
PWR TYPE REACTORS
ECCS
LOFT REACTOR
TESTING
ACCIDENTS
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety
210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Language
English
Abstract
Results from three loss of coolant experiments in the Loss of Fluid Test facility with the nuclear core at selected power levels are described. Emphasis is placed on the thermal hydraulic behavior which led to an unexpected rewetting, or early cooling, of the fuel rods prior to the action of the emergency core-cooling system. Phenomena important to the observed behavior are described.