HIGH POWER DENSITY DEVELOPMENT PROJECT. Twelfth Quarterly Progress Report, January-March 1963
- Author
- Holland, L. K.
- Published
- United States : [publisher not identified], 1963.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1963. - Physical Description
- microfiche : negative ; 8 x 13 cm
- Summary
- The number of original fuel bundles under irradiation in the VBWR core was reduced from 24 to 16 as a result of fuel rod service failures. Installation of pool facilities at Consumers Big Rock Point Reactor was completed. Thirty initial core fuel bundles were gamma scanned using the pool facilities. The fabrication of special assembly 11S was completed. The fuel rods for 11S consisted of four swaged pellet and twelve swaged powder fuel rods clad in 0.010inch thick 304-L stainless steel. Spacer and assembly hardware damage to assemblies 1S and 4S during in-core handling required fabrication of new assembly structure components. Fuel assembly 2S (swaged powder fuel) was examined after in-core sipping tests indicated possible fuel rod failures. Examination revealed one fuel rod to have a longitudinal clad crack 7 inches long. Four instrumented assemblies for Big Rock Point were calibrated for flow in the heat transfer loop under singie and two-phase flow conditions. Bearing characteristics and performance were evaluated as pant of the simulated reactor operating conditions of flow, temperature, and pressure. Stability test equipment was assembled and tested preparatory to shipping to Big Rock Point. To expand on empirical methods previously used to calculate control blade worth, three analytical methods were evaluated. Comparison between power distribution at Big Rock Point, as determined by gamma scan and the FLARE analytical method, was made, and good agreement was shown. FLARE was shown to underestimate, somewhat, the axial peaking factor, and tended to increase the power in the core bottom relative to the core top. A basic program system was checked out and run on the 312 computer at Big Rock Point. This includes the majority of the calculational packages, a basic executive control routine, and the necessary utility packages to allow the system to operate. (auth)
- Report Numbers
- GEAP-4219
- Other Subject(s)
- BEARINGS
- COMPUTERS
- CONTROL ELEMENTS
- COOLANT LOOPS
- CRACKS
- DISTRIBUTION
- FABRICATION
- FAILURES
- FLUID FLOW
- FUEL CANS
- FUEL ELEMENTS
- GAMMA RADIATION
- HEAT TRANSFER
- INSTRUMENTS
- IRRADIATION
- MEASURED VALUES
- MULTIPLICATION FACTORS
- OPERATION
- PELLETS
- PERFORMANCE
- POWDERS
- POWER PLANTS
- POWER
- PRESSURE
- PROGRAMMING
- REACTIVITY
- REACTOR CORE
- REACTOR TECHNOLOGY
- RESEARCH REACTORS
- SPACERS
- STABILITY
- STAINLESS STEELS
- TEMPERATURE
- TESTING
- VBWR
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(04-3)-361
NSA number: NSA-17-026858
OSTI Identifier 4718385
Research organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
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