Conference Articles 2019

  • Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
    Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility
    In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:117-122. https://doi.org/10.1007/978-3-030-22204-8_4
    DORA PSI
  • Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Martínez T, Aberle O, et al.
    Measurement of the 244Cm and 246Cm neutron-induced capture cross sections at the n_TOF facility
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03008 (8 pp.). https://doi.org/10.1051/epjconf/201921103008
    DORA PSI
  • Andreani M, Paranjape S
    Modelling of the interaction of two heat sources simulating the thermal effects of PARs
    Presented at: ICAPP 2019 - International congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Babiano-Suarez V, Caballero L, Domingo-Pardo C, Ladarescu I, Aberle O, Alcayne V, et al.
    Characterization and first test of an i-TED prototype at CERN n_TOF
    In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:169-173. https://doi.org/10.1007/978-3-030-22204-8_18
    DORA PSI
  • Barbagallo M, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Bécares V, et al.
    (n,cp) reactions study at the n_TOF facility at CERN: results for the cosmological lithium problem
    In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:259-264.
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). LaGrange Park, USA: American Nuclear Society (ANS); 2019:1960-1969.
    DORA PSI
  • Clifford I, Cozzo C, Ferroukhi H
    First assessments of the dynamic gap conductance model in TRACE
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:4624-4636.
    DORA PSI
  • Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
    Modeling of the U3Si2/SiC fuel system behavior for a RIA scenario
    In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
    DORA PSI
  • Fernandez Moguel L, Lind T, Rýdl A
    Analysis of fission product transport in unit 3 of Fukushima Daiichi
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:508-521.
    DORA PSI
  • Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1107-1118.
    DORA PSI
  • Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
    Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
    Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
    DORA PSI
  • Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
    Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
    Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
    DORA PSI
  • Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
    Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:024 (14 pp.).
    DORA PSI
  • Kalilainen J, Lind T, Stuckert J, Stegmaier U
    Aerosol results of the QUENCH-18 bundle test
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:019 (11 pp.).
    DORA PSI
  • Kapulla R, Paranjape S, Falsetti C, Paladino D
    High spatial resolution PIV measurements in the PANDA facility
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Lamirand V, Laureau A, Rochman D, Perret G, Gruel A, Leconte P, et al.
    An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
    DORA PSI
  • Lind T, Campbell S, Herranz LE, Kissane M, Song JH
    A summary of fission-product-transport phenomena during SGTR severe accidents
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:4063-4075.
    DORA PSI
  • Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
    Overwiew and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 3
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1133-1146.
    DORA PSI
  • Mala P, Pautz A, Ferroukhi H
    EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:1640-1649.
    DORA PSI
  • Manara D, Jacquemain D, Van Dorsselaere JP, Bottomley PD, Adorni M, Journeau C, et al.
    Severe accident research priority ranking: a new assessment eight years after the Fukushima Daiichi accident
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:1-25.
    DORA PSI
  • Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
    Data for the s process from n_TOF
    In: Formicola A, Junker M, Gialanella L, Imbriani G, eds. Nuclei in the cosmos XV. Vol. 219. Springer proceedings in physics. Cham: Springer; 2019:63-70. https://doi.org/10.1007/978-3-030-13876-9_11
    DORA PSI
  • Mora DF, Mukin R, Costa Garrido O, Niffenegger M
    Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
    In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
    DORA PSI
  • Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
    Screening analysis for pressurized thermal shock (PTS) transient scenarios
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
    DORA PSI
  • Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
    Uncertainties in pressurized thermal shock analyses
    In: Design and analysis: 4th international symposium on coke drum life cycle management. Vol. 3. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
    DORA PSI
  • Nikitin K, Clifford I, Ferroukhi H
    PMSYS: plant management system as a part of Swiss Simulation Platform
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). LaGrange Park, USA: American Nuclear Society (ANS); 2019:2943-2954.
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
     Assessment of nTRACER and parcs performance for VVER configurations
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:700-709.
    DORA PSI
  • Papadopoulos P, Tietze S, Suckow D, Ceder SJ, Roth B, Lind T
    Hydrodynamic characterisation inside a wet scrubber for different flow regimes relevant for pool scrubbing and FCVS
    In: Proceedings of the ERMSAR 2019. Prague: AF POWER agency; 2019:028 (10 pp.).
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Gas redistribution caused by interacting sources in the presence of a vertical condenser
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Pecchia M, Vasiliev A, Perret G, Ferroukhi H
    Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments
    Presented at: ICNC 2019 - 11th international conference on nuclear criticality safety; September 15-20, 2019; Paris, France.
    DORA PSI
  • Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyana Y, Gaunt R, et al.
    Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1147-1162.
    DORA PSI
  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:2209-2222.
    DORA PSI
  • Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
    Towards the validation of neutron noise simulators: qualification of data acquisition systems
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019:2638-2647.
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
    In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:47-55.
    DORA PSI
  • Scolaro A, Robert Y, Fiorina C, Clifford I, Pautz A
    Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
    In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:1174-1183.
    DORA PSI
  • Siefman D, Hursin M, Pautz A
    Data assimilation of post irradiation examination experiments to adjust fission yields
    In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2019:13004 (4 pp.). https://doi.org/10.1051/epjconf/202023913004
    DORA PSI
  • Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for unit 2
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1119-1132.
    DORA PSI
  • Tagliente G, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Babiano-Suarez V, et al.
    Nuclear astrophysics at n_TOF facility, CERN
    In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:251-258.
    DORA PSI
  • Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
    Fission program at n_TOF
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ Web of Conferences. sine loco: EDP Sciences; 2019:03006 (9 pp.). https://doi.org/10.1051/epjconf/201921103006
    DORA PSI
  • Verma V, Demazière C, Vinai P, Ricciardi G, Jacqmin R
    Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019:1124-1133.
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
    Presented at: ANS annual meeting 2019. The value of nuclear; June 9-13, 2019; Minneapolis, USA.
    DORA PSI

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