Abstract
In experiments on U crystallization in a dissolver solution containing Cs, there is concern that Cs and Pu(IV) nitrate complex are deposited on the UNH crystal in the dissolver solution at the time of the U crystallization. The characteristics of generation of Cs and Pu(IV) nitrate complex with dissolver solution of MOX fuel were examined. This complex was obtained as a precipitate by mixing dissolver solution of MOX fuel and CsNO3 solution, and was identified as dicesium tetravalent plutonium hexanitrate, Cs2Pu(NO3)6 by concentration analysis and XRD. The precipitate has a tendency to be generated at high HNO3 concentrations. Thermal analysis shows that the precipitate is stable below 245 °C, and a weight loss of 10.29 ± 0.23% is observed between 245 and 297 °C. This result indicates the decomposition of Cs2Pu(NO3)6 to Cs2PuO2(NO3)4. With these properties, the UNH crystal should melt at the condition between 60 and 100 °C and be separable from the Cs complex by filtration. This suggests a new method of crystal purification allowing higher decontamination of UNH crystal in the U crystallization process.
Original language | English |
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Pages (from-to) | 659-662 |
Number of pages | 4 |
Journal | Journal of Alloys and Compounds |
Volume | 489 |
Issue number | 2 |
DOIs | |
Publication status | Published - 2010 Jan 21 |
Keywords
- Actinide alloys and compounds
- Precipitation
- Thermal analysis
- X-ray diffraction
ASJC Scopus subject areas
- Mechanics of Materials
- Mechanical Engineering
- Metals and Alloys
- Materials Chemistry