Francesco Belloni

Person

Belloni, Francesco

  • Safety Environment & Health

Person: Employee

  1. 2014
  2. Shortcomings of 1-D thermohydraulic transient analysis for a pool type reactor (like MYRRHA)

    Di Rocco, F. & Belloni, F., 20 Jan 2014, Rome, Italy: Sapienza Università di roma. 321 p.

    Research output: ThesisMaster's thesis

  3. 2015
  4. Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

    Andreoli, F., Bisogni, D., Belloni, F. & Scheveneels, G., Aug 2015, 16th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). United States, p. 4703-4716 (NURETH - International Topical Meeting on Nuclear Reactor Thermalhydraulics; no. 16).

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

  5. 2017
  6. Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors

    Toti, A., Belloni, F. & Vierendeels, J., 1 May 2017, In: Annals of nuclear energy. 103, p. 36-48

    Research output: Contribution to journalArticlepeer-review

  7. 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

  8. 2018
  9. Extension and application on a pool-type test facility of a system thermalhydraulic/CFD coupling method for transient flow analyses

    Toti, A., Vierendeels, J. & Belloni, F., 3 Feb 2018, In: Nuclear Engineering and Design. 331, p. 83-96 14 p.

    Research output: Contribution to journalArticlepeer-review

  10. Coupled system thermal-hydraulic/CFD analysis of a protected loss of flow transient in the MYRRHA reactor

    Toti, A., Vierendeels, J. & Belloni, F., 16 Apr 2018, In: Annals of nuclear energy. 118, p. 199-211 13 p.

    Research output: Contribution to journalArticlepeer-review

  11. On the EU-Japan roadmap for experimental research on corium behavior

    Bechta, S., Ma, W-M., Miassoedov, A., Journeau, C., Okamoto, K., Manara, D., Bottomley, D., Kurata, M., Sehgal, B. R., Stuckert, J., Steinbrueck, M., Fluhrer, B., Keim, T., Fischer, M., Langrock, G., Piluso, P., Hózer, Z., Kiselova, M., Belloni, F. & Schyns, M., 9 Oct 2018, In: Annals of nuclear energy. 124, p. 541-547 7 p.

    Research output: Contribution to journalArticlepeer-review

  12. SAFEST Project on Corium Behavior in Severe Accidents

    Miassoedov, A., Fluhrer, B., Journeau, C., Bechta, S., Hózer, Z., Manara, D., Kiselova, M., Keim, T., Langrock, G., Belloni, F., Bottomley, D., Kurata, M. & Okamoto, K., 14 Dec 2018, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12). Unknown, 15 p. 113

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

  13. 2019
  14. POD-identification reduced order model of linear transport equations for control purposes

    Star, S., Belloni, F., Van den Eynde, G. & Degroote, J., 5 Mar 2019, In: International journal for numerical methods in fluids. 90, 8, p. 375-388 8 p.

    Research output: Contribution to journalArticlepeer-review

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