FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Thirteenth Quarterly Progress Report, July-September 1963

Technical Report · Tue Oct 01 04:00:00 EDT 1963

OSTI ID:4123471

Fuel irradiations in the VBWR have resulted in exposure increases of 1000 Mwd/t (average) for the lead assemblies of each type. The fuel continues to operate satisfactorily. Fuel assemblies 14J and 9H have small fission gas leakages, but no visible cracks or defects. Physical property tests on irradiated type 304 stainless steel, Zircaloy-4, and Zircaloy-2 fuel cladding were made. The residual stresses of non-irradiated stainless steel clad material were measured. The surface tensile hoop stress was variable from 43 to 2660 kg/ cm/sup 2/ for different samples. The residual hoop stresses in stainiess steel tubing were correlated to the time to failure in boiling magnesium chloride. The relative lifetimes of HPD and Fuel Cycle clad in boiling magnesium chloride do not agree with their relative lifetimes in the reactor. Stability loop data for the velocity response to a sinusoidal variation in power input are presented. The experimental and calculated results are similar in character and in frequency of the resonance response. A strong sensitivity to subcooling is shown for calculations made for the same exit quality. Tabulated data for critical heat flux in annular geometry with a rough liner is given. (N.W.R.)

• Research Organization: General Electric Co: Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-18-004761
• OSTI ID: 4123471
• Report Number(s): GEAP-4383
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
BURNOUT
BURNUP
CANNING
CONFIGURATION
CRACKS
DEFECTS
EQUATIONS
ERRORS
FAILURES
FISSION PRODUCTS
FREQUENCY
FUEL ELEMENTS
FUELS
GASES
HEAT TRANSFER
HIGH TEMPERATURE
IRRADIATION
LEAKS
MAGNESIUM CHLORIDES
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
NEUTRON FLUX
NUMERICALS
POWER PLANTS
REACTOR CORE
REACTOR OSCILLATORS
REACTOR SAFETY
REACTOR TECHNOLOGY
REPROCESSING
RESEARCH REACTORS
STABILITY
STAINLESS STEELS
STRESSES
SURFACES
TABLES
TENSILE PROPERTIES
THERMAL CONDUCTIVITY
TRANSFER FUNCTIONS
TUBES
VARIATIONS
VBWR
VELOCITY
WATER COOLANT
ZIRCALOY