RCS pressure under reduced inventory conditions following a loss of residual heat removal

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5035767

Palmrose, D E; Hughes, E D; Johnsen, G W

The thermal-hydraulic response of a closed-reactor coolant system to loss of residual heat removal (RHR) cooling is investigated. The processes examined include: core coolant boiling and steam generator reflux condensation, pressure increase on the primary side, heat transfer mechanisms on the steam generator primary and secondary sides, and effects of noncondensible gas on heat transfer processes.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5035767
• Report Number(s): EGG-M-91507; CONF-920804-21; ON: DE92017919
• Resource Relation: Conference: American Society of Mechanical Engineers national heat transfer conference and exposition, San Diego, CA (United States), 9-12 Aug 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
AFTER-HEAT REMOVAL
COOLING
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
NOZZLES
PRESSURIZERS
REACTOR SAFETY
STEAM GENERATORS
BOILERS
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled