Published 1976
| Version v1
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Preparation of uranium--plutonium mixed carbide
Description
The carbide fuel fabrication line of the Institut fuer Material- und Festkoerperforschung (IMF) is presented. The carbide fabrication by carbothermic reduction as well of original produced urania-/plutonia-Powders as of sintered oxide waste is described. Test results of the stoichiometry behavior and of the reduction of plutonium losses are given. Reduction of losses is possible by an early step of formation of mixed crystals within the carbide fabrication process. It seems possible to decrease the total material-loss to values lower than 1 wt percent if the batch size is large enough. 36 fig, 5 tables
Availability note (English)
MF available from INIS under the Report Number.
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Additional details
Additional titles
- Augmented title (English)
- IMF carbide line; Pu losses; stoichiometry
Publishing Information
- Imprint Pagination
- 39 p.
- Report number
- ORNL-tr--4180
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8281016
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- BINARY MIXTURES; DENSITY; FABRICATION; FUEL FABRICATION PLANTS; FUEL PELLETS; LOSSES; NUCLEAR FUELS; PLUTONIUM CARBIDES; SINTERING; URANIUM CARBIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; DISPERSIONS; ENERGY SOURCES; FUELS; MIXTURES; NUCLEAR FACILITIES; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; REACTOR MATERIALS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Notes
- Translation by R.G. Mansfield of report KFK--2238.