FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report No. 7, January 1962-March 1962

Technical Report · Mon Apr 30 04:00:00 EDT 1962

OSTI ID:4692501

Hodde, J.A. comp

Activities in an integrated investigation in the VBWR and other facilities to improve the technological limits of boiling reactors are reported. In work on advanced fuel power tests, reduction of VBWR stability test data is almost complete. Information is also included on the irradiation status of fuel assemblies and operation of defected fuel tests. Results of UO/sub 2/ conductivity tests in the center melting calibration assembly are reported. In research on heat transfer and fluid dynamics, a seven-rod test section was fabricated for investigation of differences between single- and multi-rod burnout heat flux. Measurements of fuel isotopic composition indicate that the capture of neutrons by U/sup 238/ to form Pu/sup 239/ may have been underestimated. (J.R.D.)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-17-022854
• OSTI ID: 4692501
• Report Number(s): GEAP-3935
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
BURNOUT
CAPTURE
FLUID FLOW
FUEL CYCLE
FUEL ELEMENTS
FUELS
HEAT TRANSFER
IRRADIATION
MELTING
NEUTRONS
PLUTONIUM 239
POWER PLANTS
REACTOR TECHNOLOGY
RODS
STABILITY
TESTING
THERMAL CONDUCTIVITY
URANIUM 238
URANIUM DIOXIDE
VBWR
WATER MODERATOR