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 |
|---|---|
| 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
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Miwa, S., Osaka, M., Nozaki, T., Arima, T., & Idemitsu, K. (2015). Oxygen potential of a prototypic Mo-cermet fuel containing plutonium oxide. Journal of Nuclear Materials, 465, 840-842. https://doi.org/10.1016/j.jnucmat.2015.06.004