1. Numerical analysis of TDS spectra under high and low flux plasma exposure conditions

    Terentyev, D., Bakaeva, A., Grigorev, P., Buzi, L., De Temmerman, G., Van Oost, G. & Noterdaeme, J-M., 20 Feb 2016, PHYSICA SCRIPTA: 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC). Vol. T167. 5 p. (Physica Scripta).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  2. Microstructure and nano-hardness of single crystal tungsten exposed to high flux deuterium plasma

    Terentyev, D., Dubinko, A., Bakaeva, A., De Temmerman, G. & Unterberg, B., 27 Nov 2017, Physica Scripta: 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC). T170 ed. Vol. 2017. p. 1-6 6 p. 014064. (Physica Scripta).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  3. High temperature nanoindentation of tungsten: Modelling and experimental validation

    Terentyev, D., Xiao, X., Lemeshko, S., Hangen, U. D. & Zhurkin, E. E., 22 Jun 2020, In : International Journal of Refractory Metals & Hard Materials. 89, p. 1-12 12 p., 105222.

    Research output: Contribution to journalArticle

  4. Assessment of mechanical properties of SPS-produced tungsten including effect of neutron irradiation

    Terentyev, D., Vilémová, M., Yin, C., Veverka, J., Dubinko, A. & Matejicek, J., Jun 2020, In : International Journal of Refractory Metals & Hard Materials. 89, p. 1-9 9 p., 105207.

    Research output: Contribution to journalArticle

  5. Development of chromium and chromium-tungsten alloy for theplasma facing components Application of vacuum arc meltingtechniques

    Terentyev, D., Khvan, T., You, J-H. & Van Steenberge, N., 5 May 2020, In : Journal of Nuclear Materials. 536, p. 1-11 11 p., 152240.

    Research output: Contribution to journalArticle

  6. Further development of large-scale atomistic modelling techniques for Fe–Cr alloys

    Terentyev, D., Bonny, G., Castin, N., Domain, C., Malerba, L., Olsson, P., Molodtsov, V. L. & Pasianot, R. C., 15 Feb 2011, In : Journal of Nuclear Materials. 409, 2, p. 167-175 9 p.

    Research output: Contribution to journalArticle

  7. Annual Scientific Report 2019: Fusion Programme SCK CEN

    Terentyev, D., 1 Sep 2020, SCK CEN. 81 p. (SCK•CEN Reports; no. BLG-1221)

    Research output: Report/bookBLG - Open report

  8. Neutron irradiation hardening across ITER diverter tungsten armor

    Terentyev, D., Yin, C., Dubinko, A., Chang, C-C. & You, J-H., 4 Oct 2020, In : International Journal of Refractory Metals & Hard Materials. 95, p. 1-11 11 p., 105437.

    Research output: Contribution to journalArticle

  9. Irradiation embrittlement in pure chromium and chromium-tungsten alloy in a view of their potential application for fusion plasma facing components

    Terentyev, D., Zinovev, A., Khvan, T., You, J-H., Van Steenberge, N. & Zhurkin, E. E., 21 May 2021, In : Journal of Nuclear Materials. 554, p. 1-11 11 p., 153086.

    Research output: Contribution to journalArticle

  10. Carbon–vacancy interaction controls lattice damage recovery in iron

    Ternon, C., Heinola, K., Bakaev, A., Zhurkin, E. & Bonny, G., Sep 2014, In : Scripta Materialia. 86, p. 9-12

    Research output: Contribution to journalArticle