INVESTIGATION OF GAS-COOLED REACTOR SAFETY PROBLEMS. Technical Progress Report, April 1, 1961-June 30, 1961

Technical Report · Mon Jul 31 04:00:00 EDT 1961

OSTI ID:4835894

Goldstein, L; Monroe, C W

The review of the safety of gas-cooled power reactors was continued. The survey concentrated on pebble-bed reactor safety, recent EGCR transient analyses, and the effectiveness of graphite surface coatings in retarding fission gas release and oxidation. The ceramic nature of the pebble-bed reactor fuel and its mobility lead to a number of safety considerations not present in other gas- cooled power reactors. Afterheat removal by natural circulation in the EGCR cannot be achieved upon loss of coolant pressure. Experimental results on the effectiveness of graphite surface coatings indicate the need for development of radiation resistant coatings. Exploratory investigations were made related to containment systems, thorium 0oppler coefficients in graphite-matrix fuels, and transient heat transfer during depressurization. (auth)

• Research Organization: United Nuclear Corp., White Plains N.Y.
• NSA Number: NSA-16-001250
• OSTI ID: 4835894
• Report Number(s): NDA-2159-2
• Country of Publication: United States
• Language: English

Related Subjects

CERAMICS
COATING
CONFIGURATION
CONVECTION
COOLANT LOOPS
COOLING
EFFICIENCY
EGCR
FAILURES
FISSION PRODUCTS
FUELS
GAS COOLANT
GAS FLOW
GASES
GRAPHITE
GRAPHITE MODERATOR
HEAT TRANSFER
LEAKS
LOSSES
MATERIALS TESTING
MEASURED VALUES
OXIDATION
PEBBLE BED
PELLETS
POROSITY
POWER PLANTS
PRESSURE
PRESSURE VESSELS
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
SHELLS
SHUTDOWN
SPECTRAL SHIFT
SURFACES
THORIUM
TRANSIENTS
VESSELS