Nuclear Materials Science

Organisational unit: Institute

  1. Degradation of First Wall Materials under ITER Relevant Loading Conditions

    Uytdenhouwen, I. & Massaut, V., 10 Feb 2011, Gent, Belgium: UGent - Universiteit Gent. 409 p.

    Research output: ThesisDoctoral thesis

  2. Strain rate and test temperature dependence on the flow properties of La2O3-doped tungsten

    Uytdenhouwen, I., Chaouadi, R., Linke, J., Massaut, V. & Van Oost, G., 15 Dec 2008, In: Advanced Materials Research. 59, p. 319-325

    Research output: Contribution to journalArticlepeer-review

  3. Dimple optimization for XPS characterization of TEXTOR tile depositions

    Uytdenhouwen, I., Gonzalez de Vicente, S. M., Coad, J. P., Van Renterghem, W., Van den Berghe, S., Van Oost, G., Massaut, V. & Chaouadi, R., Jun 2009, In: Journal of Nuclear Materials. 390-391, p. 1138-1141

    Research output: Contribution to journalArticlepeer-review

  4. Influence of recrystallization on thermal shock resistance of various tungsten grades

    Uytdenhouwen, I., Decréton, M., Hirai, T., Linke, J., Pintsuk, G., Van Oost, G. & Massaut, V., May 2007, In: Journal of Nuclear Materials. 363-365, p. 1099-1103

    Research output: Contribution to journalArticlepeer-review

  5. Installation of a plasmatron at the Belgian Nuclear Research Centre and its use for plasma-wall interaction studies

    Uytdenhouwen, I., Schuurmans, J., Decréton, M., Massaut, V., Van Oost, G. & Chaouadi, R., May 2008, Plasma and Fusion Science: 17th IAEA Technical Meeting on Research Using Small Fusion Devices. Melville, NY, United States, p. 159-165 (AIP Conference Proceedings; no. 996).

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

  6. Preliminary assessment of possible carbide formation on Be and T contaminated CFC tiles from JET

    Uytdenhouwen, I., Gonzalez de Vicente, S. M., Coad, J. P., Van Renterghem, W., Van den Berghe, S., Van Oost, G., Massaut, V. & Chaouadi, R., Jun 2009, In: fusion engineering and design. 84, 7-11, p. 1892-1895

    Research output: Contribution to journalArticlepeer-review

  7. Mechanical and microstructural changes in tungsten due to irradiation damage

    Uytdenhouwen, I., Schwarz-Selinger, T., Coenen, J. W. & Wirtz, M., 18 Jan 2016, PHYSICA SCRIPTA: 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC). Vol. T167. 6 p. (Physica Scripta).

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

  8. Non-destructive evaluation (NDE) system for the inspection of operation-induced material degradation in nuclear power plants - overview of the neutron irradation campaigns: PVP2020-21512

    Uytdenhouwen, I. & Chaouadi, R., 20 Jul 2020, ASME 2020 Pressure Vessels & Piping Conference : Pressure Vessels and Piping Division. Vol. 7. p. 1-13 13 p. V007T07A003

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

  9. Effect of neutron irradiation on the mechanical properties of an A508 CL2 and 15KH2NMFA irradiated in the NOMAD-3 rig in the BR2 cooling water

    Uytdenhouwen, I. & Chaouadi, R., 12 Jul 2021, Proceedings of the ASME 2021 Pressure Vessels & Piping Conference. PVP2021 ed. ASME - The American Society of Mechanical Engineers, p. 1-12 12 p. 61969

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

  10. Optimisation of composite metallic fuel for minor actinide transmutation in an accelerator-driven system

    Uyttenhove, W., Sobolev, V. & Maschek, W., Sep 2011, In: Journal of Nuclear Materials. 416, 1-2, p. 192-199

    Research output: Contribution to journalArticlepeer-review

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