Conference Articles 2022

  • Al-Yahia OS, Clifford I, Nikitin K, Ferroukhi H
    Parametric study on the modeling of the open passive containment cooling system (CWC)
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September 5-10, 2022; Hsinchu.
    DORA PSI
  • Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
    First 80Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process
    In: Liu W, Wang Y, Guo B, Tang X, Zeng S, eds. Symposium on nuclei in the cosmos. 16th symposium on nuclei in the cosmos, NIC-XVI 2021. Les Ulis Cedex A: EDP Sciences; 2022:11026 (8 pp.). https://doi.org/10.1051/epjconf/202226011026
    DORA PSI
  • D'Ambrosi V, Sercombe J, Beajoui S, Chaieb A, Baurens B, Largenton R, et al.
    P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel
    In: TopFuel 2022 light water reactor fuel performance conference. Illinois: American Nuclear Society; 2022:344-353. https://doi.org/10.13182/TopFuel22-38827
    DORA PSI
  • Diomidis N, Pudollek S, Wittel M, Frankl M, Vasiliev A
    Post-closure canister degradation scenarios in deep geological disposal: preliminary definition and evaluation of potential impact on reactivity
    In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(7 pp.). https://www.ans.org/pubs/proceedings/article-51979/.
    DORA PSI
  • Fogliatto E, Clifford I, Ferroukhi H, Puragliesi R
    The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35578 (14 pp.).
    DORA PSI
  • Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
    Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:2762-2772.
    DORA PSI
  • Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
    Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2762-2772. https://doi.org/10.13182/PHYSOR22-37760
    DORA PSI
  • Hursin M, Cabelloas O, Palmiotti G
    Status of the WPEC subgroup 46 efficient and effective use of integral experiments for nuclear data validation
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1095-1104. https://doi.org/10.13182/PHYSOR22-37758
    DORA PSI
  • Lee H, Vasiliev A, Ferroukhi H
    Verification of legacy methodology of minimum critical mass estimation at PSI
    Presented at: GLOBAL 2022 - sustainable energy beyond the pandemic; July 6-8, 2022; Reims.
    DORA PSI
  • Mager T, Hursin M, Fiorina C, Pautz A
    Development of a high fidelity model of the CROCUS experimental reactor
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:946-956. https://doi.org/10.13182/PHYSOR22-37250
    DORA PSI
  • Martin J-F, Ivanova T, Bess J, Carmouze C, Gan S, Wilson AR, et al.
    The OECD NEA working party on nuclear criticality safety. Recent outcome, work in progress and outlook
    In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(10 pp.). https://www.ans.org/pubs/proceedings/article-51992/.
    DORA PSI
  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    CPR estimation by CTF subchannel code with machine learning support
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September5-10, 2022; Hsinchu.
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:586-595.
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of nTRACER to COBRA-TF for full core high-fidelity analysis of VVERs
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:586-595. https://doi.org/10.13182/PHYSOR22-37390
    DORA PSI
  • Perret G, Clifford I, Ferroukhi H
    Bias and uncertainty considerations for trace predictions of RBHT reflood experiments
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (14 pp.).
    DORA PSI
  • Raffuzzi V, Sublet JC, Jouanne C, Koning A, Rochman D
    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1361-1370. https://doi.org/10.13182/PHYSOR22-37310
    DORA PSI
  • Raffuzzi V, Sublet J-C, Jouanne C, Koning A, Rochman D
    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1361-1370.
    DORA PSI
  • Scolaro A, Fiorina C, Siefman D, Hursin M, Pautz A
    Bayesian data assimilation for fuel performance based on OFFBEAT
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:3656-3665. https://doi.org/10.13182/PHYSOR22-37357
    DORA PSI
  • Scolaro A, Fiorina C, Clifford I, Brunetto E, Pautz A
    Pre-release validation database for the multi-dimensional fuel performance code OFFBEAT
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2914-2923. https://doi.org/10.13182/PHYSOR22-37789
    DORA PSI
  • Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
    Multifaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2021
    In: International conference on radiation shielding and topical meeting of the radiation protection and shielding division. Proceedings of the 14th international conference on radiation shielding and 21st topical meeting of the radiation protection and shielding division, ICRS 2022/RPSD 2022. American Nuclear Society; 2022:308-311. https://doi.org/10.13182/ICRSRPSD22-39025
    DORA PSI
  • Zahur A, Park J, Cherezov A, Jo Y, Lee D
    Reactivity initiated accident uncertainty quantification for fuel assembly with subchannel code
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1667-1676. https://doi.org/10.13182/PHYSOR22-37528
    DORA PSI

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