Comparison of processes for conversion of UO/sub 2/(NO/sub 3/)/sub 2/ into UO/sub 2/
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6886153
Nuclear fuel cycles require conversion processes in which the product from preparation of purified uranium materials is converted into the feed for the fabrication of the reactor fuel. The preferred processes for conversion of uranyl nitrate solutions into UO/sub 2/ for fabrication of nuclear fuel pellets all involve thermal decomposition of a solid into UO/sub 3/ without melting. The criteria for comparisons of eight conversion processes apply to the preparation of UO/sub 2/ suitable for pressing into fuel pellets starting with pure uranyl nitrate solutions of moderate concentrations. The conversion processes that appear most promising have striking similarities. A solid uranium compound is formed and then is thermally decomposed to UO/sub 3/ without melting. Important characteristics of the UO/sub 3/ and the subsequently formed UO/sub 2/ are derived from those of the solid that is decomposed. This relationship is not possible for a simple thermal denitration in which molten uranyl nitrate decomposes to UO/sub 3/. The reduction of the UO/sub 3/ to UO/sub 2/ and stabilization of the UO/sub 2/ are similar for all processes. The common characteristics of these conversion processes simplify the comparisons. The major differences will be in the solids preparation steps before the final thermal decomposition and in the waste treatments required. Process characteristics are listed and the similarities are indicated by a generalized flow sheet.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- OSTI ID:
- 6886153
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
Similar Records
A comparison of processes for the conversion of uranyl nitrate into ceramic-grade UO/sub 2/
Pellet fabrication development using thermally denitrated UO{sub 2} powder
Pellet fabrication development using thermally denitrated UO sub 2 powder
Journal Article
·
Wed Jun 01 00:00:00 EDT 1988
· Nucl. Technol.; (United States)
·
OSTI ID:6585859
Pellet fabrication development using thermally denitrated UO{sub 2} powder
Technical Report
·
Fri May 01 00:00:00 EDT 1992
·
OSTI ID:10144382
Pellet fabrication development using thermally denitrated UO sub 2 powder
Technical Report
·
Fri May 01 00:00:00 EDT 1992
·
OSTI ID:5418755
Related Subjects
050400* -- Nuclear Fuels-- Feed Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
COMPARATIVE EVALUATIONS
CONVERSION
CRITICALITY
ELEMENTS
FEED MATERIALS PLANTS
INDUSTRIAL PLANTS
MAINTENANCE
METALS
NATURAL URANIUM
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
PRODUCTION
SAFETY
URANIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
URANYL COMPOUNDS
URANYL NITRATES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
COMPARATIVE EVALUATIONS
CONVERSION
CRITICALITY
ELEMENTS
FEED MATERIALS PLANTS
INDUSTRIAL PLANTS
MAINTENANCE
METALS
NATURAL URANIUM
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
PRODUCTION
SAFETY
URANIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
URANYL COMPOUNDS
URANYL NITRATES