PROGRESS IN PLUTONIUM RECYCLE RESEARCH AND DEVELOPMENT

Technical Report · Fri Jul 01 04:00:00 EDT 1960

OSTI ID:4817846

Parker, H M; McEwen, L H

Presented at the International Atomic Energy Agency Symposium on Small and Mediunn Power Reactors at Vienna, Austria, September 5 to 9, 1960. Progress is reviewed on studies on recycling of plutonium in thermal reactors including treatment of plutonium as a supplement to, as well as to supplant, the use of enriched uraniunn. The recycling of plutonium in aggregations of reactors as contrasted to recycle in an isolated reactor was considered as was also the reactivity lifetime attainable with plutonium bearing fuels and the effect of enrichrnent level on plutonium fueling economics. The discussion includes physics experiments on the critical mass of H/sub 2/O-moderated, plutonium- bearing rod arrays, lattice parameter measurements, and planned use of a special critical facility for measurements on irradiated, plutonium-bearing fuel assemblies. Mentioned also are measurements of cross-sections of plutonium isotopes. lnformation is presented on the development of methods for the fabrication of plutonium -- aluminum-alloy core, Zircaloy clad, spike enrichment fuel assemblies for initial loading of the Plutonium Recycle Test Reactor. Recent progress in the development of fabrication techniques for ceramic fuel cores (cold and hot swaging; vibratory compaction) especially attractive for semi- remote fabrication of fuel containing high exposure plutonium is likewise reviewed. Fuels reprocessing research on methods attractive for use with plutonium enriched fuel cycles are highlighted; emphasis is given to fused-salt techniques focused on close-coupled recycle concepts. A summary description is provided of the plutonium enriched, 85 tube, 70 Mw, D/sub 2/O moderated Plutonium Recycle Test Reactor and of fueling plans during subsequent operation. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-16-002677
• OSTI ID: 4817846
• Report Number(s): HW-66119
• Country of Publication: United States
• Language: English

Related Subjects

ABSORPTION
ALLOYS
ALUMINUM
AUSTRIA
BURNUP
CANNING
CERAMICS
COMPACTING
CONFERENCE
CONFIGURATION
CRITICAL ASSEMBLIES
CRITICALITY
CROSS SECTIONS
ECONOMICS
ENRICHMENT
FABRICATION
FISSION
FISSIONABLE MATERIALS
FUEL ELEMENTS
FUELS
FUSED SALTS
HEAVY WATER MODERATOR
IRRADIATION
ISOTOPES
MASS
MATERIALS TESTING
MEASURED VALUES
MULTIPLICATION FACTORS
NEUTRON FLUX
PLANNING
PLUTONIUM
PLUTONIUM ALLOYS
POWER PLANTS
PRODUCTION
PROGRAMMING
PRTR
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REMOTE HANDLING
REPROCESSING
RESONANCE ESCAPE PROBABILITY
RODS
SLOWDOWN
THERMAL NEUTRONS
THERMAL UTILIZATION
TUBES
URANIUM
VIBRATI