FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Report No. 4, April 1961-June 1961

Technical Report · Tue Aug 01 04:00:00 EDT 1961

OSTI ID:4814687

Hodde, J A

Twenty-one Zircaloy-clad assemblies were fabricated and delivered to VBWR during the period. Several Zircaloy rods were damaged during a heat treatment overtemperature accident; data concerning the overtemperature effects on these rods are included. Design changes in instrumented fuel assemblies are reported, and developement of the plan of attack and core arrangement for VBWR stability testing are described. VBWR startup tests were completed. In the fuel irradiation program, stainless steel clad assemblies were irradiated to approximately 680 Mwd/t and Zircaloy fuel assemblies were irradiated to an average of 35 Mwd/t. In heat transfer and fluid dynamics development, single rod burnout tests were completed and data obtained in high pressure observational boiling experiments are summarized. In experimental physics tests are outlined and the core location specified for the two fuel assemblies to be used in the long-term reactivity experiment. The plutonium recycle program is described and working arrangements between this program and the fuel cycle program are summarized. (J.R.D.)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-16-003940
• OSTI ID: 4814687
• Report Number(s): GEAP-3781
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
BOILING
BURNOUT
BURNUP
CANNING
CONFIGURATION
FABRICATION
FLUID FLOW
FUEL ELEMENTS
FUELS
HEAT TRANSFER
HEAT TREATMENTS
HIGH TEMPERATURE
INSTRUMENTS
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MONITORING
NEUTRON FLUX
PLANNING
PLUTONIUM
POWER PLANTS
PRESSURE
RADIATION DOSES
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REMOTE CONTROL
REPROCESSING
RESEARCH REACTORS
RODS
STABILITY
STAINLESS STEELS
STARTUP
TESTING
VBWR
WATER COOLANT
ZIRCALOY