Depressurized core heatup accident scenarios in advanced modular high temperature gas cooled reactors
Conference
·
OSTI ID:5226342
The decay heat removal by a passive air colling system from a modular high tempeature gas cooled reactor during depressurized core heatup accident scenarios was analyzed. The effects of several design and operating parameters on the peak fuel and vessel temperatures were established. The results indicate that fuel and vessel temperatures remain well below failure levels and that significant safety margins exist in the key variables of decay heat and core thermal conductivities.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5226342
- Report Number(s):
- BNL-NUREG-40361; CONF-880532-16; ON: DE88002125
- Resource Relation:
- Conference: American Nuclear Society topical meeting, Seattle, WA, USA, 1 May 1988
- 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
HTGR TYPE REACTORS
REACTOR CORES
AFTER-HEAT REMOVAL
THERMAL CONDUCTIVITY
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RHR SYSTEMS
T CODES
TEMPERATURE EFFECTS
TRANSIENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MECHANICS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
THERMODYNAMIC PROPERTIES
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR CORES
AFTER-HEAT REMOVAL
THERMAL CONDUCTIVITY
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RHR SYSTEMS
T CODES
TEMPERATURE EFFECTS
TRANSIENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MECHANICS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
THERMODYNAMIC PROPERTIES
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated