Published January 1966 | Version v1
Report

Recovery of Uranium and Plutonium from Uranium Dioxide Fuels in the Engineering-scale Alpha Facility

Description

Process studies aimed at demonstrating the main steps of a fluid-bed fluoride volatility reprocessing scheme for UO2-PuO2 fuels were continued in the engineering-scale alpha facility. The primary objective of experiments performed in the facility is to investigate the possible difficulties in handling PuF6 on an engineering scale. Further objectives are to determine the feasibility of fluoride volatility process flowsheets. Initial experiments involve the processing of UO2-PuO2 fuel containing synthetic fission products (F.P.); later experiments may be made with oxide fuel having low levels of fission product activity. The major processing steps of fluoride volatility processing are: decladding, fluorination of uranium and plutonium, distillation, purification of UF6, and thermal decomposition of PuF6 to PuF4 .

Part of:
Chemical Engineering Division Semiannual Report

Additional details

Publishing Information

Imprint Title
Chemical Engineering Division Semiannual Report
Imprint Pagination
236 p.
Journal Page Range
p. 102-110
Report number
ANL--7225

Optional Information

Notes
3 fig., 3 tabs.