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Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
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Analyses of jet-buoyant flow in a multi-compartment containment using an open-source solver
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4059-4072. https://doi.org/10.13182/NURETH20-40154
DORA PSI -
Cherezov A, Vasiliev A, Ferroukhi H
Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic
Applied Sciences. 2023; 13(2): 896 (14 pp.). https://doi.org/10.3390/app13020896
DORA PSI -
Clifford I, Kral P, Vyskocil L, Pistora V, Trewin R, Filonova Y, et al.
State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5778-5790. https://doi.org/10.13182/NURETH20-40247
DORA PSI -
Clifford I, Al-Yahia OS, Ferroukhi H
TRACE investigation on the performance of passive safety condenser as ultimate heat sink
In: Proceedings of Saudi international conference on nuclear power engineering (SCOPE). sine loco: SCOPE; 2023:23220 (6 pp.).
DORA PSI -
Coindreau O, Herranz LE, Bocanegra R, Ederli S, Maccari P, Mascari F, et al.
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Annals of Nuclear Energy. 2023; 188: 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
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Dehbi A, Kapulla R
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
Nuclear Engineering and Design. 2023; 415: 112710 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112710
DORA PSI -
Dehbi A, Kapulla R
CFD simulations of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
Presented at: https://doi.org/10.13182/NURETH20-40250
DORA PSI -
Diaz J, Liu Q, Petrov V, Manera A, Sun X
High-resolution X-Ray radiography methods developed for Post-CHF experiment
Nuclear Technology. 2023; 209(10): 1442-1465. https://doi.org/10.1080/00295450.2022.2133504
DORA PSI -
Dokhane A, Vasiliev A, Hursin M, Ferroukhi H
Nuclear data effect on BWR stability parameter uncertainty at stable core conditions
Nuclear Engineering and Design. 2023; 414: 112620 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112620
DORA PSI -
Doll U, Kapulla R, Steinbock J, Dues M, Migliorini M, Zachos PK
Seeding-free inlet flow distortion measurement by filtered Rayleigh scattering: diagnostic approach and verification
In: AIAA SCITECH 2023 forum. Reston: American Institute of Aeronautics and Astronautics; 2023:714-725. https://doi.org/10.2514/6.2023-1372
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Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Advances and new ideas for neutron-capture astrophysics experiments at CERN n_TOF
European Physical Journal A: Hadrons and Nuclei. 2023; 59(1): 8 (11 pp.). https://doi.org/10.1140/epja/s10050-022-00876-7
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Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Compton imaging for enhanced sensitivity (n,γ) cross section TOF experiments: status and prospects
In: Mattoon CM, Vogt R, Escher J, Thompson I, Žugec P, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01018 (5 pp.). https://doi.org/10.1051/epjconf/202328401018
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Domingo-Pardo C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
The neutron time-of-flight facility n_TOF at CERN: recent facility upgrades and detector developments
In: 28th international nuclear physics conference (INPC 2022). Vol. 2586. Journal of physics: conference series. Bristol: IOP Publishing; 2023:012150 (11 pp.). https://doi.org/10.1088/1742-6596/2586/1/012150
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Dupont E, Otuka N, Rochman D, Nogèure G, Aberle O, Alcayne V, et al.
Overview of the dissemination of n_TOF experimental data and resonance parameters
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:18001 (4 pp.). https://doi.org/10.1051/epjconf/202328418001
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Espegren F, Suckow D, Lind T, Mantzaras J, Theile J
Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3759-3771. https://doi.org/10.13182/NURETH20-40735
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Faldella F, Eisenring S, Kim T, Doll U, Jansohn P
Turbulent flame speed and flame characteristics of lean premixed H2-CH4 flames at moderate pressure levels
In: Proceedings of ASME Turbo Expo 2023: turbomachinery technical conference and exposition. Vol. 3A. Turbo expo: power for land, sea and air. New York: American Society of Mechanical Engineers ASME; 2023:V03AT04A068 (10 pp.). https://doi.org/10.1115/gt2023-102527
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Fogliatto E, Puragliesi R, Clifford I, Ferroukhi H
Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
Annals of Nuclear Energy. 2023; 185: 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715
DORA PSI -
Fogliatto E, Clifford I
CFD simulations of the UPTF-TRAM test C1
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:606-617. https://doi.org/10.13182/NURETH20-40211
DORA PSI -
Frankl M, Wittel M, Diomidis N, Vasiliev A, Ferroukhi H, Pudollek S
Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository
Annals of Nuclear Energy. 2023; 180: 109449 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109449
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Freixa J, Martínez-Quiroga V, Perret G
Assessment of the choked flow model of RELAP5 for the application of inverse quantification methods
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5426-5439. https://doi.org/10.13182/NURETH20-40674
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Garbil R, Hadj Hassine SB, Blaise P, Ferry C, Sjöland A, Christensen P, et al.
Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
EPJ Nuclear Sciences and Technologies. 2023; 9: 2022029 (12 pp.). https://doi.org/10.1051/epjn/2022029
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García-Infantes ME, Praena P, Casanovas P, Mastromarco M, Aberle M, Alcayne M, et al.
First high resolution measurement of neutron capture resonances in 176Yb at the n_TOF CERN facility
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:09001 (5 pp.). https://doi.org/10.1051/epjconf/202328409001
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Gonzalez-Amoros J, Papadionysiou M, Kim S, Joo HG
Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis
Nuclear Science and Engineering. 2023; 197(8): 1634-1655. https://doi.org/10.1080/00295639.2022.2140577
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Grasso M, Petrov V, Manera A, Rivera Y
Experimental velocity profile reconstruction in thin water films
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:1516-1529. https://doi.org/10.13182/NURETH20-40771
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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 – overview and first results
Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
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Huang P-H, Ahn T, Manera A, Petrov V
Experimental study on the start-up characteristics and performance of a ten sodium heat pipe bundle array
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3479-3492. https://doi.org/10.13182/NURETH20-40775
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Hursin M, Zoia A, Rouchon A, Brighenti A, Zmijarevic I, Santandrea S, et al.
Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Annals of Nuclear Energy. 2023; 194: 110066 (16 pp.). https://doi.org/10.1016/j.anucene.2023.110066
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Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes
Annals of Nuclear Energy. 2023; 189: 109842 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109842
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Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V
Validation of SAM-NekRS coupling against the TALL-3D STH/CFD coupling benchmark transient
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:518-529. https://doi.org/10.13182/NURETH20-40528
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Ishikawa Y, Endo K, Narabayashi T, Suckow D, Espegren F, Lind T, et al.
Advanced FCVS system using silver zeolite AgX, AgR and XeA
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4248-4255. https://doi.org/10.13182/NURETH20-40634
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Ishikawa Y, Endo K, Kobayashi T, Narabayashi T, Kawahara Y, Suckow DJ
Advanced radioactive material removal system using silver zeolite (3) filtered containment venting system (FCVS) hydrogen measures
In: Proceedings of the 2023 30th international conference on nuclear engineering ICONE30. Vol. 30. sine loco: Japan Society of Mechanical Engineers; 2023:1-3. https://doi.org/10.1299/jsmeicone.2023.30.1620
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Jäckel BS, Birchley JC, Lind T, Steinbrück M, Park S
Nitriding model for zirconium based fuel cladding in severe accident codes
Journal of Nuclear Materials. 2023; 582: 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
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Kang S, Huang PH, Petrov V, Manera A, Ahn T, Kammenzind B, et al.
Determination of the hydrogen heat of transport in Zircaloy-4
Journal of Nuclear Materials. 2023; 573: 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
DORA PSI -
Kapulla R, Xiongguo L, Kelm S, Doll U, Paranjape S, Paladino D
Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations
Nuclear Engineering and Design. 2023; 411: 112408 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112408
DORA PSI -
Khvostov G
Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX
Journal of Nuclear Materials. 2023; 584: 154589 (8 pp.). https://doi.org/10.1016/j.jnucmat.2023.154589
DORA PSI -
Khvostov G
Calibration and validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX
Journal of Nuclear Materials. 2023; 584: 154588 (11 pp.). https://doi.org/10.1016/j.jnucmat.2023.154588
DORA PSI -
Khvostov G
Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment
Nuclear Engineering and Technology. 2023; 55(10): 3801-3807. https://doi.org/10.1016/j.net.2023.06.045
DORA PSI -
Kim T, Doll U, Faldella F, Jansohn P
Quantification of mixing quality effects on flashback limits for H2-rich fuel gases
In: Proceedings of ASME turbo expo 2023: turbomachinery technical conference and exposition (GT2023). Vol. 3A. Proceedings of the ASME turbo expo. New York: American Society of Mechanical Engineers ASME; 2023:(9 pp.). https://doi.org/10.1115/gt2023-101551
DORA PSI -
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Modeling of hydrogen behavior in liner claddings
Journal of Nuclear Materials. 2023; 573: 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
DORA PSI -
Laureau A, Gruel A, Lamirand V, Ligonnet T, Sardet A, Pautz A
Analysis of the preliminary campaign for the PETALE program
EPJ Nuclear Sciences and Technologies. 2023; 9: 25 (9 pp.). https://doi.org/10.1051/epjn/2023010
DORA PSI -
Lee H, Vasiliev A, Ferroukhi H
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
Annals of Nuclear Energy. 2023; 181: 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556
DORA PSI -
Lerendegui-Marco J, Casanovas A, Alcayne V, Aberle O, Altieri S, Amaducci S, et al.
New perspectives for neutron capture measurements in the upgraded CERN-n_TOF Facility
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01028 (6 pp.). https://doi.org/10.1051/epjconf/202328401028
DORA PSI
Prof. Dr. Andreas Pautz
Head of Center