1. Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2, French standard No.NF, ISO 21483 (2015).
2. Towards design guidelines for fast reactor oxide fuel pins with high Pu content: driving post irradiation examination by benchmarking European fuel performance codes (Oral presentation No. FR21: IAEA-CN-291/377);Blanc,2022
3. Nuclear power, Chapter 6 - Breeder Reactors;Breeze,2017
4. Auto-catalysis and Heterogeneous reactions: A first Step Towards the Design;Charlier,2017
5. Dissolution of Th1−xUxO2: effects of chemical composition and microstructure;Claparède;J. Nucl. Mater.,2015