Nuclear Materials Science

Organisational unit: Institute

  1. Modelling irradiation-induced softening in BCC iron by crystal plasticity approach

    Xiao, X., Terentyev, D., Yu, L., Song, D., Bakaev, A. & Duan, H., 23 Aug 2015, In: Journal of Nuclear Materials. 466, p. 312-315

    Research output: Contribution to journalArticlepeer-review

  2. High temperature nano-indentation of tungsten: Modelling and experimental validation

    Xiao, X., Terentyev, D., Ruiz, A., Zinovev, A., Bakaev, A. & Zhurkin, E. E., 16 Nov 2018, In: Materials Science and Engineering: A. 743, p. 106-113 8 p.

    Research output: Contribution to journalArticlepeer-review

  3. Crystal plasticity finite element method simulation for the nanoindentation of plasma-exposed tungsten

    Xiao, X., Terentyev, D., Bakaev, A., Zinovev, A., Dubinko, A. & Zhurkin, E. E., 12 Mar 2019, In: Journal of Nuclear Materials. 518, p. 334-341 8 p.

    Research output: Contribution to journalArticlepeer-review

  4. Model for the spherical indentation stress-strain relationships of ion-irradiated materials

    Xiao, X., Terentyev, D. & Yu, L., Nov 2019, In: Journal of the Mechanics and Physics of Solids. 132, p. 1-15 15 p., 103694.

    Research output: Contribution to journalArticlepeer-review

  5. Ru thin film grown on TaN by plasma enhanced atomic layer deposition

    Xie, Q., Jiang, Y. L., Musschoot, J., Deduytsche, D., Detavernier, C., Van Meirhaeghe, R. L., Van den Berghe, S., Ru, G. P., Li, B. Z. & Qu, X. P., 30 Jun 2009, In: Thin Solid Films. 517, 16, p. 4689-4693

    Research output: Contribution to journalArticlepeer-review

  6. Diffusion barrier properties of TaNx films prepared by plasma enhanced atomic layer deposition from PDMAT with N-2 or NH3 plasma

    Xie, Q., Musschoot, J., Detavernier, C., Deduytsche, D., Van Meirhaeghe, R. L., Van den Berghe, S., Jiang, Y-L., Ru, G-P., Li, B-Z. & Qu, X-P., Oct 2008, In: Microelectronic Engineering. 85, 10, p. 2059-2063

    Research output: Contribution to journalArticlepeer-review

  7. TiO(2)/HfO(2) Bi-Layer Gate Stacks Grown by Atomic Layer Deposition for Germanium-Based Metal-Oxide-Semiconductor Devices Using GeO(x)N(y) Passivation Layer

    Xie, Q., Musschoot, J., Schaekers, M., Caymax, M., Dellabie, A., Lin, D., Qu, X-P., Jiang, Y-L., Van den Berghe, S. & Detavernier, C., Jun 2011, In: Electrochemical and Solid State Letters. 14, 5, p. G27-G30

    Research output: Contribution to journalArticlepeer-review

  8. Growth kinetics and crystallization behavior of TiO2 films prepared by plasma enhanced atomic layer deposition

    Xie, Q., Musschoot, J., Deduytsche, D., Van Meirhaeghe, R. L., Detavernier, C., Van den Berghe, S., Jiang, Y-L., Ru, G-P., Li, B-Z. & Qu, X-P., Sep 2008, In: Journal of The Electrochemical Society. 155, 9, p. H688-H692

    Research output: Contribution to journalArticlepeer-review

  9. Solving the Puzzle of (100) Interstitial Loop Formation in bcc Iron

    Xu, H., Stoller, R. E., Osetsky, Y. N., Terentyev, D. & Bonny, G., 26 Jun 2013, In: Physical review Letters. 110, p. 1-5

    Research output: Contribution to journalArticlepeer-review

  10. Characterization of swift heavy ion irradiation damage in ceria

    Yablinsky, C., Devanathan, R., Pakarinen, J., Gan, J., Severin, D., Trautmann, C. & Allen, T., 4 Mar 2015, In: Journal of Materials Research. 30, 09, p. 1473-1484

    Research output: Contribution to journalArticlepeer-review

  11. 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 journalArticlepeer-review

  12. 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 journalArticlepeer-review

  13. Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

    Ye, B., Miao, Y., Shi, J., Salvato, D., Mo, K., Jamison, L., Bergeron, A., Hofmann, G. L., Leenaers, A., Oaks, A., Yacout, A. M., Van den Berghe, S., Petry, W. & Kim, Y. S., 19 Nov 2020, In: Journal of Nuclear Materials. 544, p. 1-14 14 p., 152684.

    Research output: Contribution to journalArticlepeer-review

  14. 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 journalArticlepeer-review

  15. 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 journalArticlepeer-review

  16. 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 journalArticlepeer-review

  17. 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 journalArticlepeer-review

  18. 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 journalArticlepeer-review

  19. 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

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