Conference Articles 2022

  • Ahn T, Huang P-H, Diaz J, Manera A, Petrov V
    Experimental study on start-up characteristics of a sodium-filled heat pipe, using in-house high-resolution and high-speed radiation-based imaging system
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35742 (15 pp.).
    DORA PSI
  • 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
  • Che S, Mao J, Sun X, Manera A, Petrov V
    Design of high-resolution experiments for extended LOFC accidents HTGRS
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35301 (16 pp.).
    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
  • Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
    Dynamic bias error arising from two-phase flow measurements performed with radiation transmission
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:37372 (16 pp.).
    DORA PSI
  • Diaz J, Liu Q, Petrov V, Manera A, Sun X
    High-resolution X-ray radiography methods developed for post-chf experiment
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35375 (16 pp.).
    DORA PSI
  • Diaz J, Ahn T, Adams R, Petrov V, Manera A
    High-resolution tomographic measurements of adiabatic rod bundle
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35374 (17 pp.).
    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
  • Doll U, Röhle I, Dues M
    Unsteady multi-parameter flow diagnostics by filtered Rayleigh scattering: system design by multi-objective optimisation
    In: Proceedings of the 20th international symposium on the application of laser and imaging techniques to fluid mechanics. ; 2022:(18 pp.).
    DORA PSI
  • Espegren F, Suckow D, Lind T, Mantzaras J, Theile J, Ishikawa Y, et al.
    Effectiveness of hydrogen recombination by AgX and AgR zeolites
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. sine loco: Karlsruher Institut für Technologie (KIT); 2022:330 (14 pp.).
    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
  • Gupta S, Herranz LE, Lebel LS, Sonnenkalb M, Pellegrini M, Marchetto C, et al.
    Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:33970 (16 pp.).
    DORA PSI
  • Huang PH, Ahn T, Manera A, Petrov V
    The effect of cooling efficiency on the startup characteristic and performance of the sodium heat pipes for the special purpose reactor with different filling ratio
    In: Proceedings of advances in thermal hydraulics (ATH 2022) - Embedded with the 2022 ANS annual meeting. American Nuclear Society (ANS); 2022:120-132. https://doi.org/10.13182/T126-38145
    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
  • Huxford A, Petrov V, Manera A, Grunloh T
    A spectral shift closure model for use in proper orthogonal decomposition-based reduced order models
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35387 (9 pp.).
    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
  • Lind T, Herranz LE, Sonnenkalb M, Maruyama Y
    In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:34900 (15 pp.).
    DORA PSI
  • Lind T, Kalilainen J, Nichenko S
    MSR simulation with cGEMS: salt and fission product evaporation
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:272 (12 pp.).
    DORA PSI
  • Liu X, Kelm S, Kampili M, Allelein H-J, Kapulla R, Paladino D, et al.
    Validation of a finite volume Monte Carlo solver for nongray gas radiation in containment flows
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (16 pp.).
    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
  • Malicki M, Lind T, Kalilainen J
    The parametric sensitivity analysis of FPT-1 MELCOR 2.2 input deck as a preparation for uncertainty quantification study
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:274 (14 pp.).
    DORA PSI
  • Mantzaras J, Theile J, Suckow D, Lind T, Espegren F, Ishikawa Y, et al.
    Experimental investigation of hydrogen removal WITH Ag-zeolites under severe accident conditions
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35581 (14 pp.).
    DORA PSI
  • Mao J, Petrov V, Manera A
    High-resolution experiments on flow mixing in the scaled-down upper plenum of high-temperature gas-cooled reactors under accident scenario
    In: Proceedings of advances in thermal hydraulics (ATH 2022) - Embedded with the 2022 ANS annual meeting. sine loco: American Nuclear Society (ANS); 2022:374-387. https://doi.org/10.13182/T126-37683
    DORA PSI
  • Mao J, Petrov V, Manera A, Howard T, Cetiner SM
    On the development of a novel acoustic flow meter for high-temperature gas-cooled reactors
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35300 (14 pp.).
    DORA PSI
  • Mao J, Welker Z, Nunez D, Petrov V, Manera A
    Validation of rans-based turbulence models against high-resolutional experimental data for buoyancy-driven flow with stratified fronts
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35611 (16 pp.).
    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
  • Mascari F, Bersano A, Massone M, Agnello G, Coindreau O, Beck S, et al.
    First outcomes from the phebus FPT1 uncertainty application done in the EU-MUSA project
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35666 (16 pp.).
    DORA PSI
  • Miniero L, Pandey K, Shcherbanev S, Doll U, Noiray N
    Effects of the atomization air on the topology of a Jet A-1 spray flame in a turbulent vitiated crossflow
    In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1270-1275.
    DORA PSI
  • Miniero L, Pandey K, Shcherbanev S, Noiray N, Doll U
    Tomographic reconstruction of OH density maps for Jet-A1 spray flame in a vitiated crossflow
    In: AIAA scitech forum 2022. Reston, VA: American Institute of Aeronautics and Astronautics; 2022:AIAA 2022-1873 (8 pp.). https://doi.org/10.2514/6.2022-1873
    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
  • Papadopoulos P, Prasser H-M, Lind T
    Gas-liquid mass transfer in bubbly two-phase flows using wire-mesh sensors
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (16 pp.).
    DORA PSI
  • Park S, Lind T, Birchley J, Steinbrueck M
    Current understanding of high-temperature oxidation phenomena during air ingress scenarios
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:284 (10 pp.).
    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
  • Roth B, Suckow D, Dehbi A
    Experimental study of pool scrubbing related bubble hydrodynamics in the globule flow regime
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35574 (15 pp.).
    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
  • Shcherbanev S, Morinière T, Solana-Pérez R, Doll U, Noiray N
    Flame anchoring of a premixed jet flame in vitiated crossflow using nanosecond repetitively pulsed discharge
    In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1425-1429. https://www.ecm2021napoli.eu/proceedings/.
    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
  • Vitullo F, Lamirand V, Ligonnet T, Pakari O, Godat D, Frajtag P, et al.
    Millimetric fuel rod displacements: an experimental study of the impact on local thermal neutron flux in the CROCUS reactor
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2632-2641. https://doi.org/10.13182/PHYSOR22-37846
    DORA PSI
  • Vázquez-Rodríguez C, Jiménez G, Andreani M, Paladino D, Paranjape S, Kapulla R, et al.
    Simulation of PANDA PE1 spray test using GOTHIC 8.3(QA)
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35515 (16 pp.).
    DORA PSI
  • Welker Z, Balestra P, Manera A, Petrov V
    Oxygen ingress measurements of a scales HTGR facility for small and medium break size DLOFC and air ingress accident scenarios
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35717 (12 pp.).
    DORA PSI
  • Welker Z, Balestra P, Manera A, Petrov V
    PIV measurements of a depressurizing jet to study helium-air mixing during HTGR depressurization accidents
     
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35718 (15 pp.).
    DORA PSI
  • Yeo D, Petrov V, Manera A
    Application of machine learning for online discovery of component degradation dynamics
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35385 (16 pp).
    DORA PSI
  • Yeo D, Petrov V, Manera A
    Development of the methodology for degradation emulation of primary salt pump in high-temperature fluoride salt test facility
    In: Transactions of the American nuclear society. ANS winter meeting and technology expo 2022. Vol. 127. Transactions of the American Nuclear Society. American Nuclear Society; 2022:268-271. https://doi.org/10.13182/T127-39667
    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
  • worldcupWek worldcupW, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
    very good
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35819 (15 pp.).
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