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U.S. Department of Energy
Office of Scientific and Technical Information

FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Tenth Quarterly Progress Report, October-December 1962

Technical Report ·
OSTI ID:4694551
Progress in the fuel cycle program to improve the technological limits of boiling-water reactors is reported. Irradiation of special and basic fuel assemblies is being carried out in VBWR for power-limit tests. A leak in the VBWR recirculation piping resulted primarily from mechanical and thermal plastic strain cycling. Metallographic examination of Zircaloy-clad fuel rods at the points of fretting against the wire spacers showed that mechanical wear rather than chemical attack is the dominant effect observed. Two spacers were designed to prevent fretting. Stainless steel-clad UO/sub 2/ fuel was fabricated. Meaaurements in a stability loop of oscillations of flow velocity at the entrance to the electrical heater section showed that the measured frequencies did not match the calculated resonant frequencies. This was interpreted to mean that the loop was being driven by some excitation such as the dynamic boiling process. A four-rod test section is being fabricated for heat-transfer and fluid-dynamic tests. Chemical analyses of the radial variation in isotopic composition within a fuel rod are in progress. (M.C.G.)
Research Organization:
General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
NSA Number:
NSA-17-021221
OSTI ID:
4694551
Report Number(s):
GEAP-4159
Country of Publication:
United States
Language:
English