Nuclear Materials Science

Organisational unit: Institute

  1. Article › Research
  2. Accelerator driven systems for transmutation: Fuel development,design and safety

    Maschek, W., Chen, X., Delage, F., Fernandez-Carretero, A., Haas, D., Matzerath Boccaccini, C., Rineiski, A., Smith, P., Sobolev, V., Thetford, R., Wallenius, J. & Verwerft, M., Feb 2008, In : Progress in Nuclear Energy. 50, 2-6, p. 333-340

    Research output: Contribution to journalArticle

  3. Accurate lattice parameter measurements of stoichiometric uranium dioxide

    Leinders, G., Cardinaels, T., Binnemans, K. & Verwerft, M., 17 Jan 2015, In : Journal of Nuclear Materials. 459, p. 135-142 7 p.

    Research output: Contribution to journalArticle

  4. Activated sintering of ThO2 with Al2O3 under reducing and oxidizing conditions

    Baena, A., Cardinaels, T., Verwerft, M., Vleugels, J. & Binnemans, K., 1 Mar 2016, In : Journal of Nuclear Materials. 470, p. 34-43 9 p.

    Research output: Contribution to journalArticle

  5. ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project.

    Delage, F., Belin, R., Chen, X-N., D'Agata, E., Klaassen, F., Knol, S., Maschek, W., Ottaviani, J-P., Rineiski, A. & Sobolev, V., 22 Aug 2011, In : Energy Procedia. 7, p. 303-313 11 p.

    Research output: Contribution to journalArticle

  6. Advanced atomistic models for radiation damage in Fe-based alloys: Contributions and future perspectives from artificial neural networks

    Castin, N., Pascuet, M. I., Messina, L., Domain, C., Olsson, P., Pasianot, R. C. & Malerba, L., 9 Feb 2018, In : Computational Materials Science. 148, p. 116-130

    Research output: Contribution to journalArticle

  7. ALPHABETA - a dedicated open-source tool for calculating TEM stage tilt angles

    Cautaerts, N., Delville, R. & Schryvers, D., 3 Dec 2018, In : Journal of Microscopy. 273, 3, p. 189-198 10 p.

    Research output: Contribution to journalArticle

  8. AlSi matrices for U(Mo) dispersion fuel plates

    Leenaers, A., Van den Berghe, S. & Detavernier, C., Mar 2013, In : Journal of Nuclear Materials. 439, p. 7-18

    Research output: Contribution to journalArticle

  9. Aluminum cladding oxide growth prediction for high flux research reactors

    Kim, Y. S., Chae, H. T., Van den Berghe, S., Leenaers, A., Kuzminov, V. & Yacout, A. M., 24 Nov 2019, In : Journal of Nuclear Materials. 529, p. 1-13 13 p., 151926.

    Research output: Contribution to journalArticle

  10. An intermetallic forming steel under radiation for nuclear applications

    Hofer, C., Stergar, E., Maloy, S. A., Wang, Y. Q. & Hosemann, P., Mar 2015, In : Journal of Nuclear Materials. 458, 03, p. 361-368

    Research output: Contribution to journalArticle

  11. Analysis of surface roughness influence in non-destructive magnetic measurements applied to reactor pressure vessel steels

    Vértesy, G., Gasparics, A., Griffin, J. M., Mathew, J., Fitpatrick, M. E. & Uytdenhouwen, I., 15 Dec 2020, In : Applied Sciences. 10, 24, p. 1-11 11 p., 8938.

    Research output: Contribution to journalArticle

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