Diego Castelliti

Person

Castelliti, Diego

  • Reactor Safety

Person: Employee

  1. 2019
  2. MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO

    Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K. & Tarantino, M., 3 Nov 2019, In : Nuclear Engineering and Design. 353, p. 1-10 10 p., 110270.

    Research output: Contribution to journalArticle

  3. Thermal Hydraulic Aspects of Liquid Metal Cooled Reactors

    Roelofs, F. (ed.), Van Tichelen, K., Kennedy, G., Rozzia, D., Castelliti, D., Keijers, S. & Fernandez, R., 4 Sep 2019, Duxford, UK: Woodhead publishing (imprint of Elsevier). 462 p. (Energy)

    Research output: Report/bookBook as author

  4. Calculation tool for heat exchanger tube rupture in pool-type reactors

    Castelliti, D. & Lomonaco, G., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 2384-2397 14 p.

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

  5. 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

  6. Immortal experimental loop at JAEA - Post-process and validation

    Castelliti, D., Watanabe, N., Obayashi, H., Sugawara, T., Sasa, T. & Nishihara, K., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 248-261 14 p.

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

  7. LBE-cooled scaled Pool facility E-SCAPE: Results and applications for code validation

    Castelliti, D., Van Tichelen, K. & Mirelli, F., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 1837-1850 14 p.

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

  8. MYRRHA Primary Heat Exchanger Experimental Simulations on CIRCE-HERO

    Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Caruso, G., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K. & Tarantino, M., 19 Mar 2019, SESAME International Workshop Petten, The Netherlands, 19-21 March, 2019: Workshop paper. 2019 ed. Petten, The Netherlands: Unknown, p. 1-12 12 p.

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

  9. 2018
  10. 2017
  11. Safety studies for the MYRRHA critical core with the SIMMER-III code

    Belloni, F., Castelliti, D., Schyns, M., Chen, X-N., Li, T-R., Gabrielli, F., Rineiski, A., Andriolo, L., Guo, L., Bubelis, E., Bandini, G. & Sarotto, M., 1 Dec 2017, In : Annals of nuclear energy. 110, p. 1030-1042 13 p.

    Research output: Contribution to journalArticle

  12. Hydraulic Assessment of the MYRRHA Primary Heat Exchanger

    Nalbandyan, A. & Castelliti, D., Sep 2017, FH Aachen - University of Applied Sciences. 102 p.

    Research output: ThesisMaster's thesis

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