Nuclear Materials Science

Organisational unit: Institute

  1. Chromia doped UO2 fuel: Investigation of the lattice parameter

    Cardinaels, T., Govers, K., Vos, B., Van den Berghe, S., Verwerft, M., de Tollenaere, L., Maier, G. & Delafoy, C., Mar 2012, In: Journal of Nuclear Materials. 424, 1-3, p. 252-260

    Research output: Contribution to journalArticlepeer-review

  2. Effect of sintering atmosphere on the hardness of ThO2

    Cardinaels, T., Van Eyken, J., Puzzolante, J-L., Verwerft, M., Baena, A. & Binnemans, K., 15 Aug 2016, In: Journal of Nuclear Materials. 477, p. 222-227 6 p.

    Research output: Contribution to journalArticlepeer-review

  3. Heterogeneous fuels for minor actinides transmutation: Fuel performance codes predictions in the EFIT case study

    Calabrese, R., Vettraino, F., Artioli, C., Sobolev, V., Thetford, R. & Verwerft, M., May 2010, In: Annals of nuclear energy. 37, 6, p. 867-874

    Research output: Contribution to journalArticlepeer-review

  4. The performance of the EFIT heterogeneous fuel systems: codes predictions

    Calabrese, R., Vettraino, F., Artioli, C., Sobolev, V., Thetford, R. & De Bruyn, D., Aug 2010, International Congress on Advances in Nuclear Power Plants 2009 (ICAPP 2009).. Tokyo, Japan, Vol. 3. p. 911571-911578

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

  5. Use of triflic acid in the recycling of Thoria from Nuclear Fuel Production Scrap

    Cagno, S., Gijsemans, L., Tyrpekl, V., Cardinaels, T., Verwerft, M. & Binnemans, K., 23 Jun 2017, In: Journal of Sustainable Metallurgy. 3, p. 659-667 9 p.

    Research output: Contribution to journalArticlepeer-review

  6. Atomic scale analysis of defect clustering and predictions of their concentrations in UO2+x

    Çaglak, E., Govers, K., Lamoen, D., Labeau, P-E. & Verwerft, M., Dec 2020, In: Journal of Nuclear Materials. 541, 9 p., 152403.

    Research output: Contribution to journalArticlepeer-review

  7. Lattice parameter of Am, Np bearing MOX fuel: an empirical potential study

    Çaglak, E. & Labeau, P-E., 24 Mar 2021, In: Journal of Physics Communications. 5, p. 1-8 8 p., 035012.

    Research output: Contribution to journalArticlepeer-review

  8. Atomic scale simulations on LWR and Gen-IV fuel

    Çaglak, E. & Verwerft, M., 12 Oct 2021, SCK CEN. 108 p.

    Research output: ThesisDoctoral thesis

  9. Fracture-mechanical properties of neutron irradiated ITER specification tungsten

    Caganidze, A., Chauhan, A., Schneider, H-C., Terentyev, D., Borghmans, G. & Aktaa, J., 8 Jan 2021, In: Journal of Nuclear Materials. 547, p. 1-8 8 p., 152761.

    Research output: Contribution to journalArticlepeer-review

ID: 17733