Reactor Safety

Organisational unit: Unit

  1. Total loss of flow benchmark in CIRCE-HERO integral test facility

    Lorusso P., Del Nevo, A., Narsisi, V., Giannetti, F., Caruso, G., Zwijssen, K., Breijder, P. A., Hamidouche, T., Castelliti, D., Rozzia, D. & Tarantino, M., 1 May 2021, In: Nuclear Engineering and Design. 376, p. 1-24 24 p., 111086.

    Research output: Contribution to journalArticlepeer-review

  2. 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 journalArticlepeer-review

  3. 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

  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. 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

  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. Shielding and activation calculations around the reactor core for the MYRRHA ADS design

    Ferrari, A., Mueller, S., Konheiser, J., Castelliti, D., Sarotto, M. & Stankovskiy, A., 25 Sep 2017, In: EPJ Web of Conferences. 153, p. 1-3 3 p., 05001.

    Research output: Contribution to journalArticlepeer-review

  8. 4. System thermal hydraulics for liquid metals

    Forgione, N., Castelliti, D., Gerschenfeld, A., Polidori, M., Del Nevo, A. & Hu, R., 5 Dec 2018, Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. WP - Woodhead Publishing, p. 157-184 28 p.

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

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