Nuclear Materials Science

Organisational unit: Institute

  1. Microstructural investigation and identification of intermetallic σ-phase in solution annealed 316L-type austenitic stainless steel

    Lescur, A., Stergar, E., Lim, J., Hertelé, S. & Petrov, R., 20 Oct 2021, In: Materials Characterization. 182, p. 1-8 8 p., 111524.

    Research output: Contribution to journalArticlepeer-review

  2. Effect of statistically stored dislocations in tungsten on the irradiation induced nano-hardening analyzed by different methods

    Bonny, G., Khvan, T., Bakaeva, A., Yin, C., Dubinko, A., Cabet, C., Loyer-Prost, M., Castin, N., Bakaev, A. & Terentyev, D., 1 Jan 2021, In: Journal of Nuclear Materials. 543, p. 1-8 8 p., 152543.

    Research output: Contribution to journalArticlepeer-review

  3. Analysis of environmentally assisted crack initiation of Alloy 182 in simulated light water reactor primary water with the engineering initiation model EngInit

    Vankeerberghen, M. & Bosch, R-W., 15 Oct 2021, In: Corrosion Engineering, Science and Technology. p. 1-13 13 p.

    Research output: Contribution to journalArticlepeer-review

  4. Two-step alkaline thorium dioxide precipitation A low waste method for highly sinterable ThO 2

    Wangle, T., Peeters, N., Cautaerts, N., Delloye, T., Cardinaels, T., Vleugels, J. & Verwerft, M., 2 Apr 2021, In: Journal of Nuclear Materials. 552, p. 1-10 10 p., 152984.

    Research output: Contribution to journalArticlepeer-review

  5. ZrN coating as diffusion barrier in U(Mo) dispersion fuel systems

    Leenaers, A., Ye, B., Van Eyken, J. & Van den Berghe, S., 15 Apr 2021, In: Journal of Nuclear Materials. 552, p. 1-12 12 p., 153000.

    Research output: Contribution to journalArticlepeer-review

  6. The BR2 Reactor: Short History, Characteristics and Utilization

    Van Dyck, S., 7 Jul 2021, Encyclopedia of Nuclear Energy: Reference Work 2021. Greenspan, E. (ed.). Section 11 - Research Reactors ed. Elsevier, Vol. 4. p. 96-104 9 p. (Unknown).

    Research output: Contribution to report/book/conference proceedingsChapterpeer-review

  7. 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 journalArticlepeer-review

  8. Investigating the formation mechanism of void lattice in tungsten under neutron irradiation: from collision cascades to ordered nanovoids

    Zhong-Zhu, L., Li, Y-H., Terentyev, D., Castin, N., Bakaev, A., Bonny, G., Yang, Z., Lian, L., Zhou, H-B., Gao, F. & Lu, G-H., 12 Aug 2021, In: Acta Materialia. 219, p. 1-15 15 p., 117239.

    Research output: Contribution to journalArticlepeer-review

  9. Effect of irradiation temperature on the fracture-mechanical behaviour of tungsten irradiated to 1 dpa

    Gaganidze, E., Chauhan, A., Schneider, H-C., Terentyev, D., Rossaert, B. & Aktaa, J., 19 Jul 2021, In: Journal of Nuclear Materials. 556, p. 1-6 6 p., 153200.

    Research output: Contribution to journalArticlepeer-review

  10. The Potential of the Internal Friction Technique to Evaluate the Role of Vacancies and Dislocations in the Hydrogen Embrittlement of Steels

    Vandewalle, L., Konstantinovic, M., Depover, T. & Verbeken, K., 27 Mar 2021, In: Steel Research international. 92, 6, p. 1-15 15 p., 202100037.

    Research output: Contribution to journalArticlepeer-review

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