RCS pressure under reduced inventory conditions following a loss of residual heat removal
Conference
·
OSTI ID:10164949
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:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10164949
- Report Number(s):
- EGG-M-91507; CONF-920804-21; ON: DE92017919
- Resource Relation:
- Conference: 28. national heat transfer conference,San Diego, CA (United States),9-12 Aug 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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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
STEAM GENERATORS
HYDRAULICS
HEAT TRANSFER
REACTOR SAFETY
MATHEMATICAL MODELS
PRESSURIZERS
NOZZLES
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
AFTER-HEAT REMOVAL
COOLING
STEAM GENERATORS
HYDRAULICS
HEAT TRANSFER
REACTOR SAFETY
MATHEMATICAL MODELS
PRESSURIZERS
NOZZLES
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED