Nuclear Materials Science

Organisational unit: Institute

  1. Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

    Van den Bosch, J., Bosch, R-W., Sapundjiev, D. & Al Mazouzi, A., Jun 2008, In: Journal of Nuclear Materials. 376, 3, p. 322-329

    Research output: Contribution to journalArticlepeer-review

  2. SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184 dpa at 413 °C

    Van den Bosch, J., Anderoglu, O., Dickerson, R., Hartl, M., Dickerson, P., Aguiar, J., Hosemann, P., Toloczko, M., Maloy, S. & Gavrilov, S., Sep 2013, In: Journal of Nuclear Materials. 440, 1-3, p. 91-97

    Research output: Contribution to journalArticlepeer-review

  3. Special Issue of the International Workshop on Dispersion Strengthened Steels for Advanced Nuclear Applications- DIANA

    Van den Bosch, J. (ed.), Malerba, L. (ed.) & Henry, J. (ed.), Sep 2012, In: Journal of Nuclear Materials. 428, 1-3, 192 p.

    Research output: Contribution to journalSpecial issuepeer-review

  4. Neutronic design of the XT-ADS core with In-Pile-Sections

    Van den Eynde, G., Sobolev, V., Malambu Mbala, E., Maes, D., Lamberts, D., Aït Abderrahim, H., Mansani, L., Giraud, B., Hogenbirk, A., Vaz, P., Romanets, Y., Vincente, M-C., Coddington, P., Mikityuk, K., Struwe, D., Schikorr, M., Rimpault, G. & Artioli, C., 1 Apr 2008, Utilisation and Reliability of High Power Proton Accelerators (HPPA5). Paris, France, Vol. 1. p. 357-365

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

  5. Topical Day | From nuclear data to a reliable estimate of spent fuel decay heat

    Van den Eynde, G., Gysemans, M. & Schröder, J., 26 Oct 2017, SCK CEN. 20 p. (SCK•CEN Reports; no. BA-96)

    Research output: Report/bookBook of abstractspeer-review

  6. Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel

    Van Dyck, S., Al Mazouzi, A., Rempel, A., stoenescu, R. & gavillet, D., 16 Jun 2005, Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel. Bejing, China, p. 10-4

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

  7. Characterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service

    Van Dyck, S., Al Mazouzi, A., stoenescu, R. & gavillet, D., 16 Jun 2005, Characterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service. Beijing, China, p. 10-21

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

  8. The restart of the BR2 reactor after its third refurbishment

    Van Dyck, S., 18 May 2017, Proceedings of the RRFM2017 conference. ENS - European Nuclear Society, 10 p. RRFM2017-A0032

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

  9. 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

  10. The BR2 Reactor: Short History, Characteristics and Utilization

    Van Dyck, S., 7 Jul 2021, Encyclopedia of Nuclear Energy: Reference Work 2021. Greenspan, E. (ed.). Section 11 - Research Reactors ed. Elsevier, Vol. 4. p. 96-104 9 p. (Unknown).

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

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