Francesco Belloni

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Belloni, Francesco

  • Reactor Safety

Person: Employee

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  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 journal › Article

  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 proceedings › In-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 journal › Article

  6. Development and Validation of a System Thermal-Hydraulic/CFD Codes Coupling Methodology for Multi-Scale Transient Simulations of Pool-Type Reactors

    Toti, A., Van Tichelen, K., Belloni, F., Van Tichelen, K. & Van den Eynde, G. 2 Jul 2018 UGent - Universiteit Gent. 196 p.

    Research output: Thesis › Doctoral thesis

  7. 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 journal › Article

  8. 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 journal › Article

  9. 2017

  10. 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 journal › Article

  11. 2015

  12. 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 proceedings › In-proceedings paper

  13. 2014

  14. 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: Thesis › Master's thesis

ID: 40847