USE OF PLUTONIUM AS FUEL IN NUCLEAR REACTORS. Quarterly Report No. 4, April-June 1961

Technical Report · Sat Jul 01 04:00:00 EDT 1961

OSTI ID:4803863

First results on Pu oxalate solubility show a minimum value of 21.9 mg Pu/1. Continued work on resesrch to establish the various factors affecting PuO/ sub 2/ dissolution and purification of Pu salts by ion exchangers is reported. In other work, it was found that Pu concentrations up to 10/sup -5/ g do not impede the fluorimetric determination of U. Fabrication of ceramic fuels such as plutonium carbide, UO/sub 2/--C mixtures and UO/sub 2/ is discussed along with dilatometric results on PuO/sub 2/ and PuO/sub 2/--UO/sub 2/ shapes. Investigations of dispersed fuel properties are also reported. (J.R.D.)

• Research Organization: Societe Belge pour l'Industrie Nucleaire, Brussels
• NSA Number: NSA-16-012653
• OSTI ID: 4803863
• Report Number(s): EURAEC-130
• Country of Publication: United States
• Language: English

Related Subjects

CARBON
CERAMICS
DISPERSIONS
FABRICATION
FISSIONABLE MATERIALS
FUELS
IMPURITIES
ION EXCHANGE
MATERIALS TESTING
MEASURED VALUES
OXALATES
PLUTONIUM
PLUTONIUM CARBIDES
PLUTONIUM OXIDES
QUALITATIVE ANALYSIS
REACTOR TECHNOLOGY
REACTORS
REPROCESSING
SALTS
SOLUBILITY
SOLUTIONS
URANIUM
URANIUM DIOXIDE
URANIUM FLUORIDES