Nuclear Materials Science

Organisational unit: Institute

  1. Thermal desorption spectroscopy of W–Ta alloys, exposed to high-flux deuterium plasma

    Zayachuk, Y., 't Hoen, M. H. J., Uytdenhouwen, I., Van Oost, G. & Schuurmans, J., Dec 2011, In : Physica Scripta. 2011, T145, p. 014041-014041

    Research output: Contribution to journalArticle

  2. Ductile to brittle transition in ITER specification tungsten assessed by combined fracture toughness and bending tests analysis

    Yin, C., Terentyev, D., Pardoen, T., Petrov, R. & Zhenfeng, T., 10 Feb 2019, In : Materials Science and Engineering: A. 750, p. 20-30 11 p.

    Research output: Contribution to journalArticle

  3. Tensile properties of baseline and advanced tungsten grades for fusion applications

    Yin, C., Terentyev, D., Pardoen, T., Bakaeva, A., Petrov, R., Antusch, S., Michael, R., Vilemova, M., Matejicek, J. & Zhang, T., 10 Apr 2018, In : International Journal of Refractory Metals & Hard Materials. 75, p. 153-162 10 p.

    Research output: Contribution to journalArticle

  4. Impact of neutron irradiation on the strength and ductility of pure and ZrC reinforced tungsten grades

    Yin, C., Terentyev, D., Zhang, T., Petrov, R. & Pardoen, T., 15 Aug 2020, In : Journal of Nuclear Materials. 537, p. 1-15 15 p., 152226.

    Research output: Contribution to journalArticle

  5. Anisotropy in the hardness of single crystal tungsten before and after neutron irradiation

    Yin, C., Bonny, G. & Terentyev, D., 28 Dec 2020, In : Journal of Nuclear Materials. 546, p. 1-7 7 p., 152759.

    Research output: Contribution to journalArticle

  6. Ductile to brittle transition temperature of advanced tungsten alloys for nuclear fusion applications deduced by miniaturized three-point bending tests

    Yin, C., Terentyev, D., Zhang, T., Nogami, S., Antusch, S., Chang, C-C., Petrov, R. & Pardoen, T., 9 Sep 2020, In : International Journal of Refractory Metals & Hard Materials. 95, p. 1-11 11 p., 105464.

    Research output: Contribution to journalArticle

  7. Assessment of mechanical properties of neutron irradiated tungsten and its alloys

    Yin, C. & Terentyev, D., 20 Nov 2020, UCL - Université Catholique de Louvain. 202 p.

    Research output: ThesisDoctoral thesis

  8. Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

    Ye, B., Bhattacharya, S., Mo, K., Yun, D., Pellin, M., Fortner, J., Hofmann, G., Yacout, A. M., Wiencek, T., Leenaers, A. & Van den Berghe, S., 6 May 2015, In : Journal of Nuclear Materials. 464, p. 236-244 8 p.

    Research output: Contribution to journalArticle

  9. A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power

    Ye, B., Hofmann, G. L., Leenaers, A., Bergeron, A., Kuzminov, V., Van den Berghe, S. & Kim, Y. S., 1 Feb 2018, In : Journal of Nuclear Materials. 499, p. 191-203 13 p.

    Research output: Contribution to journalArticle

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