SINTERING OF URANIUM OXIDE IN THE RANGE OF 1200-1300 C
Journal Article
·
· American Ceramic Society Bulletin (U.S.)
OSTI ID:4175312
Taking advantage of the increased sinterability of uranium oxide with an O/U ratio of 2.30 to 1, pellets of over 95% theoretical density were obtained after sintering at 1300 deg C. The nonstoichiometric uranium oxide mixture was prepared by blending UO/sub 2/ with U/sub 3/C/sub 8/. The sintered pellets were reduced to stoichiometric composition with hydrogen at a temperature of over 1200 deg C. The data reported and the process described in the manufacture of the UO/ sub 2/ pellets are based on pilot plant production operations. (auth)
- Research Organization:
- Atomics International, Canoga Park, Calif.
- NSA Number:
- NSA-14-018185
- OSTI ID:
- 4175312
- Journal Information:
- American Ceramic Society Bulletin (U.S.), Journal Name: American Ceramic Society Bulletin (U.S.) Vol. Vol: 39; ISSN ACSBA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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