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Thermodynamic considerations i n d i c a t e t h a t sodium should be favorable f o r t h e one-step reduction of UF6 t o uranium metal. A r e a c t i o n v e s s e l w a s developed f o r t h e continuous reduction o f UF6 t o metal with batch c o l l e c t i o n of t h e products, and s e v e r a l experimental t e s t s e s t a b l i s h e d t h e chemical feasibf1lt.y o f t h i s d f r e c t and continuous reduction. Up t o 93.5% o f t h e uranium ioritent o f UFs continuously reduced by sodium i n a r e a c t i o n v e s s e l was reccsered a s massive uranium metal i n t h e form o f a metal button of acceptable p u r i t y . A remaining problem i s development o f compatible m a t e r i a l s o f construction.

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UNCLASSlFlEa ORNL-3434 C-44b-Nuclear Technology-Chemistry AEC RESEARCH AND DEVELOPMENT REPORT and Chemical Engineering M-3679 (30th ed.) '!A;5

is reported. The chemical reaction of primary interest in the Fluorox program is the oxidation of UF4 with 02' 2UF4 + 02 = UO2F2 + UF6; however, to study this process at higher temperatures, the thermal decomposition of U02:F'2, 3u02F'2 = 2/3 U 8 + UF6 + 1/3 02, is being, investigated by thermogravimetric methods in the temperature range 750-900'C. A fluidized bed reactor and a flame reactor have been used successfully to perform the continuous oxidation of UF4 with 02. The 3-in. fluidized bed reactor was operated up to 825'C on both a continuous and batch basis while the flame reactor was used to continuously react finely divided UF4 with 02 in a CO-02 flame at temperatures greater than 0 1200 C. NOTICE This document contains information of a preliminary nature and was prepared primarily for internal use at the Oak Ridge National Laboratdry. Il is subject to revision or correction and therefore does not represent a final report. The information. is not to be abstracted, reprinted or otherwise given publie,diasen nation without the approval of the ORN L pate'nt brinz,k1