Sven Van den Berghe

Person

Van den Berghe, Sven

Person

  1. 2021
  2. Microstructural Changes and Chemical Analysis of Fission Products in Irradiated Uranium-7 wt.% Molybdenum Metallic Fuel Using Atom Probe Tomography

    Bachhav, M., Miller, B. D., Gan, J., Keiser, D. D., Leenaers, A., Van den Berghe, S. & Meyer, M. K., Jul 2021, In: Applied Sciences. 11, p. 1-12 12 p., 6905.

    Research output: Contribution to journalArticlepeer-review

  3. 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

  4. U(Mo) grain refinement induced by irradiation with high energy iodine

    Salvato, D., Shi, J., Breitkreutz, H., Van Renterghem, W., Baumeister, B., Schwarz, C. M., Leenaers, A., Van den Berghe, S., Detavernier, C. & Petry, W., 2 Feb 2021, In: Journal of Nuclear Materials. 548, p. 1-12 12 p., 152850.

    Research output: Contribution to journalArticlepeer-review

  5. 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., 1 Feb 2021, In: Journal of Nuclear Materials. 544, p. 1-14 14 p., 152684.

    Research output: Contribution to journalArticlepeer-review

  6. 2020
  7. 5.14 - U-Al Based Fuel System

    Leenaers, A., Wight, J., Van den Berghe, S., Ryu, H. J. & Valery, J-F., 3 Aug 2020, Comprehensive Nuclear Materials. second ed. Oxford: Elsevier, Vol. 5. p. 464-484 21 p. (Comprehensive Nuclear Materials).

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

  8. 5.15 - U-Si Based Fuel System

    Leenaers, A., Wight, J., Van den Berghe, S., Ryu, H. J. & Valery, J-F., 3 Aug 2020, Comprehensive Nuclear Materials. second ed. Oxford: Elsevier, Vol. 5. p. 485-498 14 p.

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

  9. 5.16 - U-Mo Based Fuel System

    Leenaers, A., Wight, J., Van den Berghe, S., Ryu, H. J. & Valery, J-F., 3 Aug 2020, Comprehensive Nuclear Materials. second ed. Oxford: Elsevier, Vol. 5. p. 499-530 32 p.

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

  10. Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT)

    Williams, W. J., Wachs, D. M., Okuniewski, M. A. & Van den Berghe, S., Feb 2020, In: Annals of nuclear energy. 136, p. 1-12 12 p., 107016.

    Research output: Contribution to journalArticlepeer-review

  11. A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)

    Bachhav, M., Gan, J., Keiser, D. D., Giglio, J. J., Jadernas, D., Leenaers, A. & Van den Berghe, S., 1 Jan 2020, In: Journal of Nuclear Materials. 528, 151853, p. 1-9 9 p., 151853.

    Research output: Contribution to journalArticlepeer-review

  12. 2019
  13. The initial formation stages of a nanobubble lattice in neutron irradiated U(Mo)

    Salvato, D., Leenaers, A., Van Renterghem, W. & Van den Berghe, S., 10 Dec 2019, In: Journal of Nuclear Materials. 529, p. 1-13 13 p., 151947.

    Research output: Contribution to journalArticlepeer-review

  14. Aluminum cladding oxide growth prediction for high flux research reactors

    Kim, Y. S., Chae, H. T., Van den Berghe, S., Leenaers, A., Kuzminov, V. & Yacout, A. M., 24 Nov 2019, In: Journal of Nuclear Materials. 529, p. 1-13 13 p., 151926.

    Research output: Contribution to journalArticlepeer-review

  15. Thermal-hydraulics and neutronics overview of the DISECT experiment

    Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T. L. & Boer, B., 2 Jun 2019, Transactions. 2019 ed. Vol. 120. p. 348-351 4 p.

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

  16. Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses

    Terentyev, D., Van den Berghe, S., Yin, C., Rindt, P., J. Mata, G., Hoogerhuis, P., van den Bosch, P., van Maris, M., Wirtz, M., Lopes Cardozo, N. J., van Dommelen, J. A. W. & Morgan, T. W., 14 Mar 2019, In: Nuclear Fusion. 59, p. 1-7 7 p.

    Research output: Contribution to journalArticlepeer-review

  17. Microstructure and calorimetric analysis of the UeMn binary system

    Cea, A., Leenaers, A., Van den Berghe, S. & Pardoen, T., Feb 2019, In: Journal of Nuclear Materials. 514, p. 380-392 13 p.

    Research output: Contribution to journalArticlepeer-review

  18. 2018
  19. Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor

    Kalcheva, S., Van den Branden, G., Van Dyck, S., Van den Berghe, S., Housley, G. K., Woolstenhulme, N. E., Glagolenko, I. & Cole, J. I., 21 Dec 2018, In: Annals of nuclear energy. 127, p. 303-318 16 p.

    Research output: Contribution to journalArticlepeer-review

  20. Characterization of fresh EMPIrE and SEMPER FIDELIS U(Mo)/Al fuel plates made with PVD-coated U(Mo) particles

    Iltis, X., Palancher, H., Allenou, J., Vanni, F., Stepnik, B., Leenaers, A., Van den Berghe, S., Keiser, D. D. & Glagolenko, I., 22 Nov 2018, In: EPJ N - Nuclear Sciences and Technologies. 4, p. 1-7 7 p., 49.

    Research output: Contribution to journalArticlepeer-review

  21. STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels

    He, L., Keiser Jr., D., Madden, J., Perez, E., Miller, B. D., Gan, J., Van Renterghem, W., Leenaers, A. & Van den Berghe, S., 8 Sep 2018, In: Journal of Nuclear Materials. 511, p. 174-182 9 p.

    Research output: Contribution to journalArticlepeer-review

  22. Pore pressure estimation in irradiated UMo

    Salvato, D., Leenaers, A., Van den Berghe, S. & Detavernier, C., 22 Aug 2018, In: Journal of Nuclear Materials. 510, p. 472-483 12 p.

    Research output: Contribution to journalArticlepeer-review

  23. The BR2 reactor as NSUF affiliate infrastructure

    Van Dyck, S. & Van den Berghe, S., 21 Jun 2018, Transactions of the American Nuclear Society: ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials. 2018 ed. United States, Vol. 118. p. 1638-1638 143344

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

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