Removal of the Sodium Bond from Sintered (U, Pu) C Fuel Pellets

Felix B. Litton; John H. Bender

doi:dx.doi.org/10.13182/NT68-A27994

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Home / Publications / Journals / Nuclear Technology / Volume 5 / Number 5

Removal of the Sodium Bond from Sintered (U, Pu) C Fuel Pellets

Felix B. Litton, John H. Bender

Nuclear Technology / Volume 5 / Number 5 / November 1968 / Pages 299-301

Technical Papers and Note / dx.doi.org/10.13182/NT68-A27994

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Low-temperature distillation is recommended as the method for removing sodium from sodium-bonded, sintered, mixed-carbide fuel pellets. Distillation of the sodium at 5 × 10⁻⁶ torr pressure and 485 ± 10°C has no deleterious effect on the microstructure, whereas the porosity may be altered by dissolution techniques.