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SINTERING OF URANIUM OXIDE IN HYDROGEN AT 1350 C (in French)

Journal Article · · J. Nuclear Materials
Sintering oxides of large specific surface area in argon produces a more coarse-grained product (5 to 10 mu ) than does hydrogen sintering; the density is the same in each case. Departure from stoichiometric composition of the powders does not appear to influence the density of the sintered compact. The sintering, in hydrogen, of various oxides of large specific surface area, obtained from ammonium uranate and uranium peroxide, was studied in a systematic way. With a given specific surface area, the final density varied is a function of the sintering temperature, with a maximum density for a particular temperature. This temperature is lowest when the specific surface area of the powder is the greatest. A process is described for the preparation of uranium oxide powder from ammonium uranate and its sintering in hydrogen at 1350 deg C; in this way a fine-grained product of density 10.6 can be obtained. (auth)
Research Organization:
Centre d'Etudes Nucleaires, Saclay, France
NSA Number:
NSA-14-004378
OSTI ID:
4222705
Journal Information:
J. Nuclear Materials, Journal Name: J. Nuclear Materials Vol. Vol: 1
Country of Publication:
Country unknown/Code not available
Language:
French