1. The dominant mechanisms for the formation of solute-rich clusters in low-Cu steels under irradiation

    Castin, N., Bonny, G., Bakaev, A., Bergner, F., Domain, C., Hyde, J. M., Messina, L., Radiguet, B. & Malerba, L., 3 Jul 2020, In : Materials Today Energy. 100472.

    Research output: Contribution to journalArticle

  2. Modelling phase separation in Fe–Cr system using different atomistic kinetic Monte Carlo techniques

    Castin, N., Bonny, G., Terentyev, D., Lavrentiev, M. Y. & Nguyen-Manh, D., 2011, In : Journal of Nuclear Materials. 417, 1-3, p. 1086-1089 4 p.

    Research output: Contribution to journalArticle

  3. MYRRHA Primary Heat Exchanger design

    Castelliti, D. & Fernandez, R., Feb 2012, Working Material - T. M. on Innovative HX and SG design for fast reactors. Vienna, Austria, Vol. 1. p. 1-16

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

  4. GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides

    Castelliti, D., Bomboni, E., Cerullo, N., Lomonaco, G., Parisi, C. & Arien, B., 2 Mar 2009, In : Science and Technology of Nuclear Installations. 2009, 1, p. 1-8

    Research output: Contribution to journalArticle

  5. MYRRHA/FASTEF Safety Analysis in Sub-critical and Critical Mode

    Castelliti, D. & Arien, B., 13 May 2013, NURETH-15 Book of Abstracts. Pisa, Italy, Vol. 1. p. 375-375

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

  6. A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle

    Castelliti, D. & Lomonaco, G., 15 Aug 2016, In : Nuclear Engineering and Design. 305, p. 179-190 12 p.

    Research output: Contribution to journalArticle

  7. Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D models on steady state and PLOF transient

    Castelliti, D. & Hamidouche, T., 1 Jan 2016, In : Nuclear Technology. 196, 1, p. 36-46 11 p.

    Research output: Contribution to journalArticle

  8. H2020 MYRTE CIRCE-HERO experimental campaign: Post-test activity and code validation

    Castelliti, D., Hamidouche, T., Lorusso, P. & Tarantino, M., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 5029-5042 14 p.

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