A new method for UF6 conversion to UO2 with excellent characteristics
Creators
Description
Several wet and dry methods for the conversion of UF6 to UO2 powder, e.g., the ammonium diuranate (ADU) process and the integrated dry route process, have been developed to an industrial scale. Although the UO2 powders fabricated by conventional methods have good ceramic characteristics, there is room for improvement. To extend burnup of nuclear fuel, a decrease in fission gas release from UO2 pellets is required. It has been considered that large-grain pellets satisfy this requirement, but it is difficult to obtain such large-grain pellets by using conventional UO2 powder. A new method has been developed to produce a highly active UO2 powder that can greatly contribute to improvement of the fabrication process of nuclear fuel pellet. By using this highly active UO2 powder, large-grain pellets can be made easily, and low-temperature sintering can be achieved
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 56
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 90-91
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 12-16 Jun 1988.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21007825
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FABRICATION; FISSION PRODUCT RELEASE; FUEL PELLETS; NUCLEAR FUELS; PERFORMANCE; POWDER METALLURGY; PRODUCTION; SINTERING; URANIUM DIOXIDE; URANIUM FLUORIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FLUORIDES; FLUORINE COMPOUNDS; FUELS; HALIDES; HALOGEN COMPOUNDS; MATERIALS; METALLURGY; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- CONF-880601--.