Francesco Belloni

Person

Belloni, Francesco

  • Reactor Safety

Person: Employee

  1. 2019
  2. 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 journalArticle

  3. 2018
  4. 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 paper

  5. 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 journalArticle

  6. 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 journalArticle

  7. 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 journalArticle

  8. 2017
  9. 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 journalArticle

  10. 2015
  11. 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 paper

  12. 2014
  13. 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

ID: 40847