FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961

Technical Report · Tue Oct 31 00:00:00 EST 1961

DOI:https://doi.org/10.2172/4835066· OSTI ID:4835066

The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass flow rate; this result was contradictory to several previous correlations. The experimental phase of the high-pressure observational boiling experiment was completed. Reproducibility of the burnout points was good (about plus or minus 1 1/2%). High speed movies of the flow conditions at burnout are being analyzed. (auth)

• Research Organization: General Electric Co. Atomic Power Equipment Dept. San Jose, Calif.
• DOE Contract Number: AT(04-3)-189
• NSA Number: NSA-15-030204
• OSTI ID: 4835066
• Report Number(s): GEAP-3709
• Resource Relation: Other Information: Project Agreement No. 11. Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ANALOG SYSTEMS
BOILING
BURNOUT
CANNING
COMPUTERS
DISTRIBUTION
EQUATIONS
FLUID FLOW
FREQUENCY
FUEL CANS
FUEL ELEMENTS
HEATING
HYDRAULICS
INSPECTION
INSTRUMENTS
IRRADIATION
MEASURED VALUES
NEUTRON FLUX
OSCILLATIONS
PHOTOGRAPHY
PRESSURE
REACTIVITY
REACTOR CORE
REACTORS
RESONANCE ESCAPE PROBABILITY
RODS
STAINLESS STEELS
STEAM
TESTING
VARIATIONS
VBWR
WATER COOLANT
WATER MODERATOR
ZIRCALOY
ZIRCONIUM ALLOYS
ZONES