Nuclear Materials Science

Organisational unit: Institute

  1. Quantification of uranium, plutonium, neodymium and gadolinium for the characterization of spent nuclear fuel using isotope dilution HPIC-SF-ICP-MS

    Wanna, N., Dobney, A., Van Hoecke, K., Vasile, M. & Vanhaecke, F., 1 Jan 2021, In: Talanta. 221, 11 p., 121592.

    Research output: Contribution to journalArticlepeer-review

  2. Simulation of a LBLOCA in the CALLISTO test facility using the best estimate computer code RELAP5/SCDAP3.2

    Wéber, M., Hadjam, A., Souidi, F. & Vanleeuw, D., 14 May 2013, In: Nuclear Engineering and Design. 262, September 2013, p. 153-167

    Research output: Contribution to journalArticlepeer-review

  3. LWR fuel power transient testing at SCK•CEN

    Wéber, M., Benoit, P., Gouat, P., Vermeeren, L., Kuzminov, V., Kalcheva, S., Koonen, E., Cardinaels, T. & Verwerft, M., Sep 2010, Proceedings of the 2010 LWR Fuel Performance Meeting/Top Fuel/WRFPM. United States, p. 414-420

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

  4. Boundary conditions for separation and conditioning: ASOF deliverable D4.1

    Weetjens, E., Govaerts, J., Perko, J., Van Hecke, K. & Govers, K., 28 May 2019, Studiecentrum voor Kernenergie. 52 p. (SCK•CEN Reports; no. ER-0537)

    Research output: Report/bookER - External reportpeer-review

  5. Voorbereidende studie van de koud plasma modus van een ICP-QMS voor de bepaling van Fe-55, Ni-59 en Ni-63

    Wijnen, M. & Van Bree, P., Jun 2009, Antwerpen, Belgium: AP - Artesis Plantijn Hogeschool Antwerpen. 84 p.

    Research output: ThesisMaster's thesis

  6. 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

  7. 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

  8. Thermal shock response of deformed and recrystallized tungsten

    Wirtz, M., Cempura, G., Linke, J., Pintsuk, G., Uytdenhouwen, I. & Massaut, V., 18 Jun 2013, In: fusion engineering and design. 88, 9-10, p. 1768-1772

    Research output: Contribution to journalArticlepeer-review

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