FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Report No. 5, July 1961-September 1961

Technical Report · Tue Oct 10 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4804304· OSTI ID:4804304

Hodde, J.A. ed.

Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The three instrumented fuel assemblies were assembled and calibrated. Equipment and procedures have been prepared for the VBWR stability tests. Forty-two assemblies were irradiated during the last VBWR run. Average exposure for all assemblies which have been irradiated are tabulated. Detailed examination of the centermelt calibration assembly is in progress. Preliminary metallography indicates that centermelting did not occur. The conductivity of UO/sub 2/ is appreciably higher than the design basis of 1.1 Btu/hr-ft/sup 2/ ( f F/ft). This result indicates that the fuel performance limit is higher than the burnout heat flux limit. Heat Transfer and Fluid Dynamics. Use of a rough'' liner in the single rod test section resulted in a l0 to 43% increase in burnout heat flux at various operating conditions. The high-speed movies of the high pressure observational boiling experiments have been edited and assembled. Analytic work is being continued. A theoretical analysis of two-phase pressure drop and density distribution has been made. Experimental Physics. Isotopic analyses of unirradiated fuel pellets show good uniformity. Preliminary calculations of expected isotopic compositions during irradiation are being made. (auth)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-16-006217
• OSTI ID: 4804304
• Report Number(s): GEAP-3835
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
BURNOUT
CONFIGURATION
COOLANT LOOPS
DENSITY
DISTRIBUTION
EQUATIONS
FABRICATION
FAILURES
FLUID FLOW
FUEL ELEMENTS
HEAT TRANSFER
HIGH TEMPERATURE
INSTRUMENTS
IRRADIATION
ISOTOPES
LABORATORY EQUIPMENT
MATERIALS TESTING
MEASURED VALUES
MELTING
METALLOGRAPHY
MONITORING
NEUTRON FLUX
NUMERICALS
PELLETS
PLANNING
POWER PLANTS
PRESSURE
RADIATION DOSES
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REPROCESSING
RODS
STABILITY
STANDARDS
TABLES
THERMAL CONDUCTIVITY
URANIUM DIOXIDE
VARIATIONS
VBWR
WATER COOLANT
ZONES