Abstract
Oxygen potential of a prototypic Mo-cermet fuel containing 50 vol.% PuO2-x were investigated by the thermogravimetric analysis in the temperature range from 1273 K to 1473 K. It was shown that the oxygen potential and oxidation rate of the Mo-cermet were the same as those of pure PuO2-x below the oxygen potential of Mo/MoO2 oxidation reaction. The same features of the Mo-cermet sample containing 50 vol.% PuO2-x with those of pure PuO2-x were discussed in terms of the microstructure.
Original language | English |
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Pages (from-to) | 840-842 |
Number of pages | 3 |
Journal | Journal of Nuclear Materials |
Volume | 465 |
DOIs | |
Publication status | Published - Oct 1 2015 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering