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

Technical Report ·
OSTI ID:4814687

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.
DOE Contract Number:
AT(04-3)-189
NSA Number:
NSA-16-003940
OSTI ID:
4814687
Report Number(s):
GEAP-3781
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English