Combustion synthesis of (U,Pu)O 2 solid solution: from parametric study to sintered pellet
Abstract
powder was selected for pressing tests and sintering due to its industrial interest for the production of MOX fuel for PWR reactors. It was possible to obtain a pellet with a density of 88%TD, characterized by a low-temperature sintering due to the nanometric size of the powder. Despite presenting large macropores, due to the presence of residual carbon in the powder before sintering, the sintered pellet presents the expected round-shaped pores and a very homogeneous plutonium distribution.
Fields of Study & Subjects
Nuclear Materials and Properties
Rare-earth and actinide compounds
Radioactive element chemistry and processing
Publication details
- Journal / source
- Dalton Transactions
- Publisher
- Royal Society of Chemistry (RSC)
- Volume
- 55
- Issue
- 7
- Pages
- 2948–2963
- Publication date
- 1 January 2026
- Language
- EN