Journal publications of the Laboratory for Reactor Physics and Thermal-Hydraulics

Our scientists, post docs and students regularly publish articles in scientific magazines primarily in the nuclear engineering and technical field. For this purpose, each submitted article is first thoroughly reviewed and then approved.  

Here you will find a selection of journals that regularly publish articles from our laboratory:
 

2023

  • Ahn T, Diaz J, Adams R, Petrov V, Manera A
    Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
    Nuclear Technology. 2023. https://doi.org/10.1080/00295450.2023.2197680
    DORA PSI
  • Al-Yahia OS, Clifford I, Bissels W-M, Suckow D, Ferroukhi H
    Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
    Nuclear Engineering and Design. 2023; 405: 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224
    DORA PSI
  • Al-Yahia OS, Clifford I, Nikitin K, Liu P, Ferroukhi H
    TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
    Nuclear Engineering and Design. 2023; 406: 112234 (21 pp.). https://doi.org/10.1016/j.nucengdes.2023.112234
    DORA PSI
  • Alhassan E, Rochman D, Vasiliev A, Koning AJ, Ferroukhi H
    TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV
    Applied Radiation and Isotopes. 2023; 198: 110832 (15 pp.). https://doi.org/10.1016/j.apradiso.2023.110832
    DORA PSI
  • Bourdot Dutra C da S, Merzari E, Acierno J, Kraus A, Manera A, Petrov V, et al.
    High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors
    Nuclear Technology. 2023. https://doi.org/10.1080/00295450.2023.2181040
    DORA PSI
  • Breitenmoser D, Prasser HM, Manera A, Petrov V
    Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography
    International Journal of Multiphase Flow. 2023; 161: 104382 (10 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2023.104382
    DORA PSI
  • Cavaliere A, Marone F, Cozzo C, Buchanan K, Lorrette C, Pouchon MA
    FEM heat transfer modelling with tomography-based SiCf/SiC unit cell
    High Temperatures-High Pressures. 2023; 52(2): 95-110. https://doi.org/10.32908/hthp.v52.1281
    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
  • 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
    DORA PSI
  • Coppo Leite V, Merzari E, Mao J, Petrov V, Manera A
    High-fidelity simulation of mixing phenomena in large enclosures
    Nuclear Science and Engineering. 2023. https://doi.org/10.1080/00295639.2023.2186159
    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. https://doi.org/10.1080/00295450.2022.2133504
    DORA PSI
  • 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
    DORA PSI
  • D’Ambrosi V, Sercombe J, Bejaoui S, Chaieb A, Baurens B, Largenton R, et al.
    P2M simulation exercise on past fuel melting irradiation experiments
    Nuclear Technology. 2023. https://doi.org/10.1080/00295450.2023.2194270
    DORA PSI
  • 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
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    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 – overview and first results
    Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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. https://doi.org/10.1016/j.net.2023.06.045
    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
  • Malicki M, Lind T
    Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation
    Nuclear Engineering and Technology. 2023; 55(7): 2504-2515. https://doi.org/10.1016/j.net.2023.04.003
    DORA PSI
  • Malicki M, Lind T
    Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
    Progress in Nuclear Energy. 2023; 158: 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
    DORA PSI
  • Mao J, Che S, Petrov V, Manera A
    Benchmark experiments for turbulent mixing in the scaled-down upper plenum of high-temperature gas-cooled reactors under accident scenario
    Nuclear Science and Engineering. 2023. https://doi.org/10.1080/00295639.2023.2186726
    DORA PSI
  • Mao J, Vishwakarma V, Welker Z, Tai CK, Bolotnov IA, Petrov V, et al.
    Validation of RANS-based turbulence models against high-resolution experiments and DNS for buoyancy-driven flow with stratified fronts
    Nuclear Science and Engineering. 2023. https://doi.org/10.1080/00295639.2023.2241800
    DORA PSI
  • Mascari F, Bersano A, Adorni M, D'Ovidio G, Martín-Fuertes F, Jin XZ, et al.
    Current status of MELCOR 2.2 for fusion safety analyses
    Fusion Engineering and Design. 2023; 194: 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869
    DORA PSI
  • Michalopoulou V, Stamatopoulos A, Diakaki M, Tsinganis A, Vlastou R, Kokkoris M, et al.
    Measurement of the neutron-induced fission cross section of 230Th at the CERN n_TOF facility
    Physical Review C: Nuclear Physics. 2023; 108(1): 014616 (15 pp.). https://doi.org/10.1103/PhysRevC.108.014616
    DORA PSI
  • Miniero L, Pandey K, Fredrich D, Shcherbanev S, Doll U, Giusti A, et al.
    Air-blast atomization and ignition of a kerosene spray in hot vitiated crossflow
    Combustion and Flame. 2023; 256: 112915 (13 pp.). https://doi.org/10.1016/j.combustflame.2023.112915
    DORA PSI
  • Müller A, Okur F, Aribia A, Osenciat N, Vaz CAF, Siller V, et al.
    Benchmarking the performance of lithiated metal oxide interlayers at the LiCoO2|LLZO interface
    Materials Advances. 2023; 4(9): 2138-2146. https://doi.org/10.1039/d3ma00155e
    DORA PSI
  • Otten S, Kario A, Wessel WAJ, Leferink J, Ten Kate HHJ, Daly M, et al.
    Training curves of Nb3Sn Rutherford cables with a wide range of impregnation materials measured in the BOX facility
    IEEE Transactions on Applied Superconductivity. 2023; 33(5): 4003605 (5 pp.). https://doi.org/10.1109/TASC.2023.3267051
    DORA PSI
  • Paladino D, Kapulla R, Paranjape S, Suter S, Hug C, Chae M-S, et al.
    PANDA experimental database and further needs for containment analyses
    Nuclear Engineering and Design. 2023; 404: 112173 (18 pp.). https://doi.org/10.1016/j.nucengdes.2023.112173
    DORA PSI
  • Pandey K, Miniero L, Doll U, de Oliveira PM, Mastorakos E, Noiray N
    Topological transitions of Jet A-1 lean azimuthal flames (LEAF)
    Proceedings of the Combustion Institute. 2023; 39(4): 4791-4799. https://doi.org/10.1016/j.proci.2022.08.034
    DORA PSI
  • Patronis N, Mengoni A, Goula S, Aberle O, Alcayne V, Altieri S, et al.
    Status report of the n_TOF facility after the 2nd CERN long shutdown period
    EPJ Techniques and Instrumentation. 2023; 10(1): 13 (10 pp.). https://doi.org/10.1140/epjti/s40485-023-00100-w
    DORA PSI
  • Pelloni S, Rochman D
    Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region
    Annals of Nuclear Energy. 2023; 182: 109603 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109603
    DORA PSI
  • Rochman D, Taforeau J, Simeonov T, Shama A
    Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods
    Nuclear Engineering and Design. 2023; 410: 112392 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112392
    DORA PSI
  • Rochman DA, Álvarez-Velarde F, Dagan R, Fiorito L, Häkkinen S, Kromar M, et al.
    On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
    EPJ Nuclear Sciences and Technologies. 2023; 9: 14 (24 pp.). https://doi.org/10.1051/epjn/2022055
    DORA PSI
  • Seidl M, Schillebeeckx P, Rochman D
    Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel
    Frontiers in Energy Research. 2023; 11: 1143312 (15 pp.). https://doi.org/10.3389/fenrg.2023.1143312
    DORA PSI
  • Shama A, Caruso S, Rochman D
    Analyses of the bias and uncertainty of SNF decay heat calculations using Polaris and ORIGEN
    Frontiers in Energy Research. 2023; 11: 1161076 (18 pp.). https://doi.org/10.3389/fenrg.2023.1161076
    DORA PSI
  • Siefman D, Hursin M, Percher C, Heinrichs D
    Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws
    Nuclear Science and Engineering. 2023; 197: 14-24. https://doi.org/10.1080/00295639.2022.2103344
    DORA PSI
  • Sosnin NV, Lederer-Woods C, Krtička M, Garg R, Dietz M, Bacak M, et al.
    Measurement of the 77Se (n, γ) cross section up to 200 keV at the n_TOF facility at CERN
    Physical Review C: Nuclear Physics. 2023; 107(6): 065805 (9 pp.). https://doi.org/10.1103/PhysRevC.107.065805
    DORA PSI
  • Tai CK, Mao J, Petrov V, Manera A, Bolotnov IA
    Study of stable stratification in HiRJET facility with direct numerical simulation
    Nuclear Science and Engineering. 2023. https://doi.org/10.1080/00295639.2023.2197656
    DORA PSI
  • Torres-Sánchez P, Praena J, Porras I, Sabaté-Gilarte M, Lederer-Woods C, Aberle O, et al.
    Measurement of the 14N(n, p) 14C cross section at the CERN n_TOF facility from subthermal energy to 800 keV
    Physical Review C: Nuclear Physics. 2023; 107(6): 064617 (15 pp.). https://doi.org/10.1103/PhysRevC.107.064617
    DORA PSI
  • Ukleev V, Burian M, Gliga S, Vaz CAF, Rösner B, Fainozzi D, et al.
    Effect of intense x-ray free-electron laser transient gratings on the magnetic domain structure of Tm:YIG
    Journal of Applied Physics. 2023; 133(12): 123902 (6 pp.). https://doi.org/10.1063/5.0119241
    DORA PSI
  • Vocke M, Kapulla R, Morton C, Klein M, Martinuzzi RJ
    Advection-based temporal reconstruction technique for turbulent velocity fields
    Physics of Fluids. 2023; 35(1): 015123 (18 pp.). https://doi.org/10.1063/5.0129564
    DORA PSI
  • Ványi AS, Hursin M, Czifrus S
    Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor
    Annals of Nuclear Energy. 2023; 194: 110072 (15 pp.). https://doi.org/10.1016/j.anucene.2023.110072
    DORA PSI
  • Ványi AS, Hursin M, Aszódi A, Adorján L, Biró B, Magyar B, et al.
    Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor
    Annals of Nuclear Energy. 2023; 189: 109839 (12 pp.). https://doi.org/10.1016/j.anucene.2023.109839
    DORA PSI
  • Vázquez-Rodríguez C, Andreani M, Jiménez G, Kapulla R, Paranjape S, Manuel Martín-Valdepeñas J, et al.
    Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – simulations using GOTHIC8.3(QA)
    Nuclear Engineering and Design. 2023; 403: 112120 (20 pp.). https://doi.org/10.1016/j.nucengdes.2022.112120
    DORA PSI
  • Vázquez-Rodríguez C, Kapulla R, Paranjape S, Andreani M, Jiménez G, Martín-Valdepeñas JM, et al.
    Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I - experimental results
    Nuclear Engineering and Design. 2023; 412: 112453 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112453
    DORA PSI
  • Wolfertz A, Adams R, Perret G, Lamirand V
    Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2023; 1053: 168385 (12 pp.). https://doi.org/10.1016/j.nima.2023.168385
    DORA PSI
  • Wolfertz A, Perret G, Adams R
    Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
    Annals of Nuclear Energy. 2023; 188: 109792 (10 pp.). https://doi.org/10.1016/j.anucene.2023.109792
    DORA PSI

 

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  • Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
    Iterative Bayesian Monte Carlo for nuclear data evaluation
    Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
    DORA PSI
  • Alyammahi N, Yoon HJ, Al-Yahia OS, Leung R
    The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
    Nuclear Engineering and Design. 2022; 397: 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
    DORA PSI
  • Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
    Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
    European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
    DORA PSI
  • Cozzo C, Khvostov G, Clifford I, Ferroukhi H
    Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
    Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
    DORA PSI
  • Di Giuli M, Malicki M, Dejardin P, Corda V, Swaidan AM
    MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
    Nuclear Engineering and Design. 2022; 387: 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248
    DORA PSI
  • Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
    Development of a more accurate dynamic bias error model for two-phase flow measurements performed with radiation transmission
    International Journal of Multiphase Flow. 2022; 146: 103881 (22 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103881
    DORA PSI
  • Dokhane A, Vasiliev A, Hursin M, Rochman D, Ferroukhi H
    A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
    Nuclear Engineering and Technology. 2022; 54(5): 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
    DORA PSI
  • Dokhane A, Vasiliev A, Ferroukhi H
    On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999
    Nuclear Engineering and Design. 2022; 399: 112016 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112016
    DORA PSI
  • Doll U, Migliorini M, Baikie J, Zachos PK, Röhle I, Melnikov S, et al.
    Non-intrusive flow diagnostics for unsteady inlet flow distortion measurements in novel aircraft architectures
    Progress in Aerospace Sciences. 2022; 130: 100810 (24 pp.). https://doi.org/10.1016/j.paerosci.2022.100810
    DORA PSI
  • Doll U, Röhle I, Dues M, Kapulla R
    Time-resolved multi-parameter flow diagnostics by filtered Rayleigh scattering: system design through multi-objective optimisation
    Measurement Science and Technology. 2022; 33(10): 105204 (12 pp.). https://doi.org/10.1088/1361-6501/ac7cca
    DORA PSI
  • Downing JR, Petrov V, Manera A
    3D field data of flow structures in dead-ended, coolant loop reactor branch lines for CFD validation of thermal fatigue onset modeling
    Nuclear Engineering and Design. 2022; 399: 112012 (10 pp.). https://doi.org/10.1016/j.nucengdes.2022.112012
    DORA PSI
  • Fagnoni F, Konarski P
    Hydrogen degassing of zirconium under high-vacuum conditions
    Metals. 2022; 12(5): 868 (9 pp.). https://doi.org/10.3390/met12050868
    DORA PSI
  • Fiorina C, Clifford I, Kelm S, Lorenzi S
    On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
    Nuclear Engineering and Design. 2022; 387: 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
    DORA PSI
  • Fogliatto EO, Clausse A, Teruel FE
    Development of a double-MRT pseudopotential model for tridimensional boiling simulation
    International Journal of Thermal Sciences. 2022; 179: 107637 (13 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107637
    DORA PSI
  • Janasz F, Prasser H-M, Suckow D, Mityakov A
    The use of a novel gradient heat flux sensor for characterization of reflux condensation
    Nuclear Engineering and Design. 2022; 395: 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885
    DORA PSI
  • Jang J, Hursin M, Lee W, Pautz A, Papadionysiou M, Ferroukhi H, et al.
    Analysis of Rostov-II benchmark using conventional two-step code systems
    Energies. 2022; 15(9): 3318 (24 pp.). https://doi.org/10.3390/en15093318
    DORA PSI
  • Jansson P, Bengtsson M, Bäckström U, Álvarez-Velarde F, Čalič D, Caruso S, et al.
    Blind benchmark exercise for spent nuclear fuel decay heat
    Nuclear Science and Engineering. 2022; 196(9): 1125-1145. https://doi.org/10.1080/00295639.2022.2053489
    DORA PSI
  • Kalilainen J, Lind T
    Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
    Annals of Nuclear Energy. 2022; 166: 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740
    DORA PSI
  • Kapulla R, Paranjape S, Doll U, Kirkby E, Paladino D
    Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
    Nuclear Engineering and Technology. 2022; 54(11): 4348-4358. https://doi.org/10.1016/j.net.2022.07.001
    DORA PSI
  • Kapulla R, Doll U, Kirkby E, Paranjape S, Paladino D
    Growth laws and self-similarity in the confined mixing zone of unstratified and strongly stably stratified isokinetic mixing-layers past a splitter plate
    Physics of Fluids. 2022; 34(3): 035129 (16 pp.). https://doi.org/10.1063/5.0082950
    DORA PSI
  • Kapulla R, Paranjape S, Fehlmann M, Suter S, Doll U, Paladino D
    The effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility
    Nuclear Engineering and Technology. 2022; 54(6): 2311-2320. https://doi.org/10.1016/j.net.2021.12.032
    DORA PSI
  • Khvostov G
    Modelling effects of transient FGR in LWR fuel rods during a LOCA
    Journal of Nuclear Materials. 2022; 559: 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
    DORA PSI
  • Maestre J, Bahamonde C, Lamas Garcia I, Kershaw K, Biancacci N, Busom J, et al.
    High intensity proton beam impact at 440 GeV/c on Mo and Cu coated CfC/graphite and SiC/SiC absorbers for beam intercepting devices
    Journal of Instrumentation. 2022; 17: P01019 (32 pp.). https://doi.org/10.1088/1748-0221/17/01/P01019
    DORA PSI
  • Mager T, Fiorina C, Hursin M, Pautz A
    Investigation and validation of unstructured mesh methodologies for modeling experimental reactors
    Energies. 2022; 15(4): 1512 (11 pp.). https://doi.org/10.3390/en15041512
    DORA PSI
  • Mao J, Petrov V, Manera A, Howard TK, Cetiner SM
    On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
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  • Adams R, Günther C, Höflich N, Pooth O
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  • Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
    Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
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    Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
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    Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
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  • Morató S, Bernal Á, Miró R, Roman JE, Verdú G
    Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
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    Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
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    Assessment of nTRACER and PARCS performance for VVER configurations
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    Gas mixing caused by interacting heat sources PART I: experiments
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    Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
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    Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
    Annals of Nuclear Energy. 2020; 145: 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
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    The joint evaluated fission and fusion nuclear data library, JEFF-3.3
    European Physical Journal A: Hadrons and Nuclei. 2020; 56(7): 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9
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    Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
    Nuclear Engineering and Design. 2020; 356: 110365 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110365
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  • Rochman D, Koning AJ, Sublet J-C
    A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
    Nuclear Data Sheets. 2020; 163: 163-190. https://doi.org/10.1016/j.nds.2019.12.003
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Seidl M, Basualdo J
    Improvement of PIE analysis with a full core simulation: the U1 case
     
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  • Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
    Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
    European Physical Journal Plus. 2020; 135: 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
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  • Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
    Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
    Annals of Nuclear Energy. 2020; 148: 107727 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107727
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
    Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
    Annals of Nuclear Energy. 2020; 148: 107756 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107756
    DORA PSI
  • Sakellarakis VD, Vera-Tudela W, Doll U, Ebi D, Wright YM, Boulouchos K
    The effect of high-pressure injection variations on the mixing state of underexpanded methane jets
    International Journal of Engine Research. 2020; 22(9): 2900-2918. https://doi.org/10.1177/1468087420960895
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    The OFFBEAT multi-dimensional fuel behavior solver
    Nuclear Engineering and Design. 2020; 358: 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
    DORA PSI
  • Shcherbanev S, Morinière T, Solana-Pérez R, Weilenmann M, Xiong Y, Doll U, et al.
    Anchoring of premixed jet flames in vitiated crossflow with pulsed nanosecond spark discharge
    Applications in Energy and Combustion Science. 2020; 1-4: 100010 (14 pp.). https://doi.org/10.1016/j.jaecs.2020.100010
    DORA PSI
  • Siefman D, Hursin M, Perret G, Pautz A
    Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
    Progress in Nuclear Energy. 2020; 121: 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
    DORA PSI
  • Siefman D, Hursin M, Sjostrand H, Schnabel G, Rochman D, Pautz A
    Data assimilation of post-irradiation examination data for fission yields from GEF
    EPJ Nuclear Sciences and Technologies. 2020; 6: 52 (17 pp.). https://doi.org/10.1051/epjn/2020015
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  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
    Annals of Nuclear Energy. 2020; 135: 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
    DORA PSI
  • Solans V, Rochman D, Ferroukhi H, Vasiliev A, Pautz A
    Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
    Nuclear Engineering and Design. 2020; 370: 110897 (11 pp.). https://doi.org/10.1016/j.nucengdes.2020.110897
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  • 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 2 - results of severe accident analyses for unit 2
    Nuclear Engineering and Design. 2020; 369: 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
    DORA PSI
  • Soubelet B, Adams R, Kromer H, Prasser H-M
    Calibration technique and sample measurement database for material decomposition imaging using a compact deuterium-deuterium (D-D) fast neutron generator
    Radiation Physics and Chemistry. 2020; 176: 108930 (18 pp.). https://doi.org/10.1016/j.radphyschem.2020.108930
    DORA PSI
  • Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
    A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
    Annals of Nuclear Energy. 2020; 144: 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
    DORA PSI
  • Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
    A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
    IEEE Transactions on Nuclear Science. 2020; 67(4): 625-635. https://doi.org/10.1109/TNS.2020.2977530
    DORA PSI
  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    Statistical burnup distribution of moving pebbles in the HTR-PM reactor
    Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021108 (14 pp.). https://doi.org/10.1115/1.4044910
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 971: 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
    DORA PSI

 

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  • Andreani M, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, Herranz LE, et al.
    Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
    Nuclear Engineering and Design. 2019; 354: 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Application of causality analysis on nuclear reactor systems
    Chaos: An Interdisciplinary Journal of Nonlinear Science. 2019; 29(4): 043126 (16 pp.). https://doi.org/10.1063/1.5083905
    DORA PSI
  • Clifford I, Pecchia M, Mukin R, Cozzo C, Ferroukhi H, Gorzel A
    Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
    Annals of Nuclear Energy. 2019; 130: 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
    DORA PSI
  • Dehbi A, Kelm S, Kalilainen J, Mueller H
    The influence of thermal radiation on the free convection inside enclosures
    Nuclear Engineering and Design. 2019; 341: 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Lind T
    Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
    Annals of Nuclear Energy. 2019; 130: 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Lind T
    Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
    Annals of Nuclear Energy. 2019; 123: 59-77. https://doi.org/10.1016/j.anucene.2018.09.008
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  • Gallego-Marcos I, Kudinov P, Villanueva W, Kapulla R, Paranjape S, Paladino D, et al.
    Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments
    Nuclear Engineering and Design. 2019; 347: 67-85. https://doi.org/10.1016/j.nucengdes.2019.03.011
    DORA PSI
  • Griffin PJ, Koning AJ, Rochman D
    Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
    IEEE Transactions on Nuclear Science. 2019; 66(7): 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
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  • Hennig D, Lange C, Rizwan-uddin, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
    Progress in Nuclear Energy. 2019; 115: 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
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  • Hennig D, Rizwan-uddin, Lange C, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
    Progress in Nuclear Energy. 2019; 113: 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
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  • Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
    The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
    Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
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  • Koning AJ, Rochman D, Sublet J-C, Dzysiuk N, Fleming M, van der Marck S
    TENDL: complete nuclear data library for innovative nuclear science and technology
    Nuclear Data Sheets. 2019; 155: 1-55. https://doi.org/10.1016/j.nds.2019.01.002
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  • Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
    Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
    Applied Radiation and Isotopes. 2019; 145: 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
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  • Lind T, Guentay S, Herranz LE, Suckow D
    A summary of the ARTIST: aerosol retention during SGTR severe accident
    Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
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  • Nikitin K, Mueller P, Bruder A, Walser S, Judd J, Hiltbrand D
    BWR-4 ATWS modeling with RELAP5-S3K
    Nuclear Engineering and Design. 2019; 344: 38-45. https://doi.org/10.1016/j.nucengdes.2019.01.023
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  • Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
    Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
    Nuclear Technology. 2019; 205(1-2): 153-173. https://doi.org/10.1080/00295450.2018.1505356
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  • Paranjape S, Mignot G, Kapulla R, Paladino D
    Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
    Nuclear Engineering and Design. 2019; 342: 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017
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  • Park J, Kim W, Hursin M, Perret G, Vasiliev A, Rochman D, et al.
    Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
    Annals of Nuclear Energy. 2019; 131: 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
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  • Pecchia M, Ferroukhi H, Vasiliev A, Grimm P
    Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
    Annals of Nuclear Energy. 2019; 129: 67-78. https://doi.org/10.1016/j.anucene.2019.01.047
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  • Pelloni S, Rochman D
    Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
    Annals of Nuclear Energy. 2019; 129: 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
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  • Perret G, Wicaksono D, Clifford ID, Ferroukhi H
    Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
    Nuclear Technology. 2019; 205(12): 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
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  • Rochman D, Vasiliev A, Ferroukhi H, Pelloni S, Bauge E, Koning A
    Correlation ν̅ p – σ for U-Pu in the thermal and resonance neutron range via integral information
    European Physical Journal Plus. 2019; 134: 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
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  • Shama A, Pouchon MA, Clifford I
    Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
    Additive Manufacturing. 2019; 26: 1-14. https://doi.org/10.1016/j.addma.2018.12.011
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  • Skorek T, de Crécy A, Kovtonyuk A, Petruzzi A, Mendizábal R, de Alfonso E, et al.
    Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
    Nuclear Engineering and Design. 2019; 354: 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
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  • Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
    Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
    Radiation Physics and Chemistry. 2019; 156: 292-299. https://doi.org/10.1016/j.radphyschem.2018.11.017
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  • Sublet J-C, Bondarenko IP, Bonny G, Conlin JL, Gilbert MR, Greenwood LR, et al.
    Neutron-induced damage simulations: beyond defect production cross-section, displacement per atom and iron-based metrics
    European Physical Journal Plus. 2019; 134(7): 350 (50 pp.). https://doi.org/10.1140/epjp/i2019-12758-y
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  • Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
    Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
    Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
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  • Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
    Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
    Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
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  • Vasiliev A, Herrero J, Pecchia M, Rochman D, Ferroukhi H, Caruso S
    Preliminary assessment of criticality safety constraints for swiss spent nuclear fuel loading in disposal canisters
    Materials. 2019; 12(3): 494 (30 pp.). https://doi.org/10.3390/ma12030494
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  • Yang J, Suckow D, Lind T, Prasser H-M
    Study of level swell for a Filtered Containment Venting System at the VEFITA facility
    Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
    DORA PSI

 

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Time-Resolved Fast Neutron Radiography Of Air-Water Two-Phase Flows
R Zboray, V Dangendorf, I Mor, B Bromberger, K Tittelmeier, H-M Prasser
Physics Procedia 69, 551 (2015).
http://dx.doi.org/10.1016/j.phpro.2015.07.078

Boron Dilution Transient Simulation Analyses In A Pwr With Neutronics/Thermal-Hydraulics Coupled Codes In The Nurisp Project
G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Annals of Nuclear Energy Vol. 84, Pp. 86-97 (2015)

Advanced Calculation Methodology For Manufacturing And Technological Parameters’ Uncertainties Propagation At Arbitrary Level Of Lattice Elements Grouping
M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Journal of Nuclear Science And Technology, Vol. 52:7-8, Pp. 1084-1092, (2015)

Comparative assesment of PSI Air oxidation model implementation in SCDAPSim 3.5, MELCOR 1.8.6 and MELCOR 2.1
L. Fernandez-Moguel
Annals of Nuclear Energy 81, 134
http://dx.doi.org/10.1016/j.anucene.2015.03.015

 

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Break-Up and Bounce of TiO2 Agglomerates by Impaction
M. Ihalainen, T.M. Lind, A. Arffman, T. Torvela, J.K. Jokiniemi
Aerosol Science and Technology 48, 31
http://dx.doi.org/10.1080/02786826.2013.852155

Conclusions on severe accident research priorities
W. Klein-Heßling, M. Sonnenkalb, D. Jacquemain, B. Clément, E. Raimond, H. Dimmelmeier, G. Azarian, G. Ducros, C. Journeau, L.E. Herranz Puebla, A. Schumm, A. Miassoedov, I. Kljenak, G. Pascal, S. Bechta, S. Güntay, M.K. Koch, I. Ivanov, A. Auvinen, I. Lindholm
Annals of Nuclear Energy 74, 4
http://dx.doi.org/10.1016/j.anucene.2014.07.015

Synthesis of spent fuel pool accident assessments using severe accident codes
J. Fleurot, I. Lindholm, N. Kononen, B.S. Jäckel, A. Kaliatka, J. Duspiva, M. Steinbrück, T. Hollands
Annals of Nuclear Energy 74, 58
http://dx.doi.org/10.1016/j.anucene.2014.07.011

Experimental study on bounce of submicron agglomerates upon inertial impaction
M. Ihalainen, T.M. Lind, J. Ruusunen, P. Tiitta, A. Lahde, T. Torvela, J. Jokiniemi
Powder Technology 268, 203
http://dx.doi.org/10.1016/j.powtec.2014.08.029

Significance of Phébus-FP results for plant safety in Switzerland
J.C. Birchley, S. Güntay
Annals of Nuclear Energy 61, 206
http://dx.doi.org/10.1016/j.anucene.2013.02.032

Granular flow in pebble-bed nuclear reactors: Scaling,dust generation, and stress
C.H. Rycroft, A. Dehbi, T.M. Lind, S. Güntay
Nuclear Engineering and Design 265, 69
http://dx.doi.org/10.1016/j.nucengdes.2013.07.010

On the adequacy of wall functions to predict condensation rates fromsteam-noncondensable gas mixtures
A. Dehbi
Nuclear Engineering and Design 265, 25
http://dx.doi.org/10.1016/j.nucengdes.2013.07.014

A Method to Study Agglomerate Breakup and Bounce During Impaction
M. Ihalainen, T.M. Lind, T. Torvela, K.E.J. Lehtinen, J.K. Jokiniemi
Aerosol Science and Technology 46, 990
http://dx.doi.org/10.1080/02786826.2012.685663

Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
D. Bottomley, J. Stuckert, P. Hofmann, L. Tocheny, M. Hugon, C. Journeau, B. Clement, S. Weber, S. Güntay, Z. Hozer, L.E. Herranz, A. Schumm, F. Oriolo, E. Altstadt, M. Krause, M. Fischer, V.B. Khabensky, S.V. Bechta, M.S. Veshchunov, A.V. Palagin, A.E. Kiselev, V.I. Nalivaev, A.V. Goryachev, V. Zhdanov, V. Baklanov
Nuclear Engineering and Design 252, 226
http://dx.doi.org/10.1016/j.nucengdes.2012.07.006

LWR severe accident simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
N. Girault, L. Bosland, S. Dickinson, F. Funke, S. Güntay, L.E. Herranz, D. Powers
Nuclear Engineering and Design 243, 371
http://dx.doi.org/10.1016/j.nucengdes.2011.11.011

Effect Of Pump-Induced Cold-Leg Swirls On The Flow Field In The Rpv Of The Epr - Cfd Investigations And Comparison With Experimental Results
V. Petrov, A. Manera
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1476-1485 (2011)

Verification Of A Trace Epr Model On The Basis Of A Scaling Calculation Of An Sbloca Rosa Test
J. Freixa, A. Manera
Nuclear Engineering And Design, Volume 241, Issue 3, March 2011, P 888-896 (2011)

Modeling And Validation Of A Mechanistic Tool (Mefisto) For The Prediction Of Critical Power In Bwr Fuel Assemblies
C. Adamsson, J-M. Le Corre
Nuclear Engineering And Design, Vol. 241, Issue 8, Pp 2843-2858, August 2011

First principles Investigation Of Higher Oxides Of Uranium And Neptunium: U3o8 And Np20
Y. Yun, J. Rusz, M-T. Suzuki, P.M. Oppeneer
Physical Review, B 83, 075109, Doi: 10.1103/Phyrevb.83.075109(2011)

Sustainable integration of EU research in severe accident phenomenology and management
J.P. Van Dorsselaere, T. Albiol, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Nuclear Engineering and Design 241, 3451
http://dx.doi.org/10.1016/j.nucengdes.2011.01.053

Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO (TM) cladding tubes in comparison with results of previous QUENCH tests
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Nuclear Engineering and Design 241, 3224
http://dx.doi.org/10.1016/j.nucengdes.2011.05.004

Analyses of the Phebus FPT3 Experiment using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE and MELCOR
G. Repetto, O. De Luze, T. Drath, M.K. Koch, T. Hollands, K. Trambauer, C. Bals, H. Austregesilo, J.C. Birchley
Nuclear Technology 176, 352

The Once-through Mode of Steam Generator Refulx Condensation in Loss-of-Coolant Accident Scenarios
Y. Liao, S. Güntay, D.J. Suckow
Nuclear Technology 175, 510

Prediction of extrathoracic aerosol deposition using RANS-Random Walk and LES approaches
A. Dehbi
Aerosol Science and Technology 45, 555
http://dx.doi.org/10.1080/02786826.2010.550962

Improvements Of The One-Dimensional Dissolved Solute Convection Equation Using The Quickest-Ultimate Algorithm
D. Bertolotto, A. Manera, R. Macian-Juan, R. Chawla
Nuclear Engineering and Design,
http://dx.doi.org/10.1016/J.Nucengdes.2010.10.021 (2010)

Performance Of A Monte-Carlo Solution To The H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
A. Vasiliev, H. Ferroukhi, E. Kolbe
Annals of Nuclear Energy 37(2010), Pp. 1404-1410, 2010

First_principles Study Of Helium Behavior In Nuclear Fuel Materials
Y. Yun, O. Eriksson, P. M. Oppeneer
Chapter 7, Nova Science Publishers, Helium: Characteristics, Compounds And Applications, Isbn:978-1-61761-213-8 (2010)

Main Results Of Phase Iv Bemuse Project. Simulation Of Lbloca In A Npp
M. PéRez, F. ReventóS, L. Batet, R. Pericas, I. Toth, P. Bazin, CréCy. De, Germain. A, Borisov. P, Glaeser. S, Skorek. H, Joucla. T, Probst. J, Ui. P, Chung. A, Oh. B, Y. D, M. Kyncl, R. Pernica, A. Manera, F. D'Auria, A. Petruzzi, Nevo. Del,
Science And Technology of Nuclear Installations (Issn 1687-6075), Vol. 2010, Id 219294 (2010)

Experimental and calculation results of the integral reflood test QUENCH-14 with M5 (R) cladding tubes
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Annals of Nuclear Energy 37, 1036
http://dx.doi.org/10.1016/j.anucene.2010.04.015

Aerosol behavior during SIC control rod failure in QUENCH-13 test
T.M. Lind, A.P. Csordas, I. Nagy, J. Stuckert
Journal of Nuclear Materials 397, 92
http://dx.doi.org/10.1016/j.nucmat.2009.12.013

Implementation of a generalized diffusion layer model for condensation into MELCOR
K. Hogan, Y. Liao, B. Beeny, K. Vierow, R.Jr. Cole, L.L. Humphries, R.O. Gauntt
Nuclear Engineering and Design 240, 3202
http://dx.doi.org/10.1016/j.nucengdes.2010.05.059

De-agglomeration mechanisms of TiO2 aerosol agglomerates in PWR steam generator tube rupture conditions
T.M. Lind, Y. Ammar, A. Dehbi, S. Güntay
Nuclear Engineering and Design 240, 2046
http://dx.doi.org/10.1016/j.nucengdes.2010.03.002

Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
T.J. Haste, J.C. Birchley, M. Richner
Nuclear Engineering and Design 240, 1599
http://dx.doi.org/10.1016/j.nucengdes.2010.02.006

Influence of corium oxidation on fission product release from molten pool
S.V. Bechta, E.V. Krushinov, S.A. Vitol, V.B. Khabensky, S.Y. Kotova, A.A. Sulatsky, V.V. Gusarov, V.I. Almyashev, G. Ducros, C. Journeau, D. Bottomley, B. Clement, L.E. Herranz, S. Güntay, K. Trambauer, A. Auvinen, V.V. Bezlepkin
Nuclear Engineering and Design 240, 1229
http://dx.doi.org/10.1016/j.nucengdes.2010.01.008

Benchmark study on fuel bundle degradation in the Pebus FPT2 test using state-of-the-art severe accident analysis codes
B. Tóth, A. Bieliauskas, G. Bandini, J.C. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer
Nuclear Technology 169, 81
http://epubs.ans.org/download/?a=9354

Validation against DNS statistics of the normalized Langevin model for particletransport in turbulent channel flows
A. Dehbi
Powder Technology 200, 60
http://dx.doi.org/10.1016/j.powtec.2010.02.009

Monodisperse fine aerosol generation using fluidized bed
T.M. Lind, S. Danner, S. Güntay
Powder Technology 199, 232
http://dx.doi.org/10.1016/j.powtec.2010.01.011

Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident
P. Giordano, A. Auvinen, G. Brillant, J. Colombani, N. Davidovich, R. Dickson, T.J. Haste, T. Kärkelä, J.S. Lamy, C. Mun, D. Ohai , Y. Pontillon, M. Steinbrück, N. Vér
Progress in Nuclear Energy 52, 109
http://dx.doi.org/10.1016/j.pnucene.2009.09.011

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
R. Dubourg, H. Austregesilo, C. Bals, M. Barrachin, J.C. Birchley, T.J. Haste, J.S. Lamy, T.M. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer, A. Vimi
Progress in Nuclear Energy 52, 97
http://dx.doi.org/10.1016/j.pnucene.2009.09.012

B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments
G. Repetto, O. De Luze, N. Seiler, K. Trambauer, H. Austregesilo, J.C. Birchley, S. Ederli, J.S. Lamy, B. Maliverney, T. Drath, T. Hollands
Progress in Nuclear Energy 52, 37
http://dx.doi.org/10.1016/j.pnucene.2009.09.017

High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
M. Steinbrück, J.C. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hózer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov
Progress in Nuclear Energy 52, 19
http://dx.doi.org/10.1016/j.pnucene.2009.07.012

Ranking of severe accident research priorities
B. Schwinges, C. Journeau, T.J. Haste, L. Meyerd, W. Tromm, K. Trambauer
Progress in Nuclear Energy 52, 11
http://dx.doi.org/10.1016/j.pnucene.2009.09.006

SARNET: Severe accident research network of excellence
T. Albiol, J.P. Van Dorsselaere, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Progress in Nuclear Energy* 52, 2
http://dx.doi.org/10.1016/j.pnucene.2009.07.011

 

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    DORA PSI
  • Ma W, Bubelis E, Karbojian A, Sehgal BR, Coddington P
    Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis
    Nuclear Engineering and Design. 2006; 236(13): 1422-1444. https://doi.org/10.1016/j.nucengdes.2006.01.006
    DORA PSI
  • Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
    Advanced foil activation techniques for the measurement of within-pin distributions of the 63Cu(n,γ)64Cu reaction rate in nuclear fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 562(1): 393-400. https://doi.org/10.1016/j.nima.2006.03.004
    DORA PSI
  • Mikityuk K, Coddington P, Bubelis E, Chawla R
    Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
    Nuclear Engineering and Design. 2006; 236(23): 2452-2473. https://doi.org/10.1016/j.nucengdes.2006.03.012
    DORA PSI
  • Murphy MF, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, et al.
    Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples
    Annals of Nuclear Energy. 2006; 33(9): 760-765. https://doi.org/10.1016/j.anucene.2006.04.003
    DORA PSI
  • Paratte JM, Früh R, Kasemeyer U, Kalugin MA, Timm W, Chawla R
    A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor
    Annals of Nuclear Energy. 2006; 33(8): 739-748. https://doi.org/10.1016/j.anucene.2005.09.012
    DORA PSI
  • Pelloni S, Bubelis E, Mikityuk K, Coddington P
    Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast
    Annals of Nuclear Energy. 2006; 33(6): 499-509. https://doi.org/10.1016/j.anucene.2006.01.002
    DORA PSI
  • Pelloni S, Coddington P
    On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores
    Annals of Nuclear Energy. 2006; 33(17-18): 1360-1367. https://doi.org/10.1016/j.anucene.2006.10.001
    DORA PSI
  • Plaschy M, Jatuff F, Grimm P, Tani F, Jacot-Guillarmod R, Giust F, et al.
    Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2006; 43(11): 1298-1310. https://doi.org/10.3327/jnst.43.1298
    DORA PSI
  • Romano A, Li J, Yip S
    Atomistic simulation of rapid compression of fractured silicon carbide
    Journal of Nuclear Materials. 2006; 352(1-3): 22-28. https://doi.org/10.1016/j.jnucmat.2006.02.038
    DORA PSI
  • Romano A, Wallin H, Zimmermann MA, Chawla R
    Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
    Nuclear Engineering and Design. 2006; 236(3): 284-294. https://doi.org/10.1016/j.nucengdes.2005.08.007
    DORA PSI
  • Tani F, Jatuff F, Chawla R
    Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly
    Annals of Nuclear Energy. 2006; 33(6): 490-498. https://doi.org/10.1016/j.anucene.2006.02.005
    DORA PSI
  • Wenger HU, Al Mazouzi A, Atchison F, Burghartz M, Chawla R, Günther-Leopold I, et al.
    Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry
    Nuclear Physics A. 2006; 764: 1-14. https://doi.org/10.1016/j.nuclphysa.2005.08.023
    DORA PSI
  • Zilio VO, Joneja OP, Popowski Y, Rosenfeld A, Chawla R
    Absolute depth-dose-rate measurements for an 192Ir HDR brachytherapy source in water using MOSFET detectors
    Medical Physics. 2006; 33(6): 1532-1539. https://doi.org/10.1118/1.2198168
    DORA PSI

Operation Conditions Of A Phase Doppler Anemometer: Droplet Size Measurements With Laser Beam Power, Photomultiplier Voltage, Signal Gain And Signal-To-Noisle Ratio As Parameters
R Kapulla, SB Najera
Measurement Science & Technology 17, 221-227 (2006).
http://dx.doi.org/10.1088/0957-0233/17/1/034

Simulating Large-Scale Bubble Plumes Using Various Closure And Two-Phase Turbulence Models
R Zboray, Cachard de,
Nuclear Engineering And Design 235, 867-884 (2005).
http://dx.doi.org/10.1016/j.nucengdes.2004.11.008

Experimental Investigation Of Natural-Circulation Flow Behavior Under Low-Power/Low-Pressure Conditions In The Large-Scale Panda Facility
O Auban, D Paladino, R Zboray
Nuclear Technology 148, 294-312 (2004).
http://dx.doi.org/10.13182/NT04-A3568

Decobi: Investigation Of Melt Coolability With Bottom Coolant Injection
D Paladino, SA Theerthan, BR Sehgal
Progress In Nuclear Energy 40, 161-206 (2002).
http://dx.doi.org/10.1016/S0149-1970(01)00022-1

Study Of The Pwr Rea Pulse Width For Realistic Uo2 And Mox Core Designs Using 3-D Kinetics
H. Ferroukhi, M.A. Zimmermann
Annals of Nuclear Energy, Volume 36, Issue 8, Pp. 1170-1183, August 2009

Advanced Microchannel Heat Exchanger With S-Shaped Fins
N. Tsuzuki, Y. Kato, K. Nikitin, T. Ishizuka
Journal of Nuclear Science And Technology, 46(5), 403-412 (2009)

Sbloca With Boron Dilution In Pressurized Water Reactors. Impact On Operation And Safety
J. Freixa, F. ReventóS, C. Pretel, L. Batet, I. Sol
Nuclear Engineering and Des. (Issn 0029-5493), 239(4), 749-760 (2009)


AgInCd control rod failure in the QUENCH-13 bundle test
L. Sepold, T.M. Lind, A.P. Csordas, U. Stegmaier, M. Steinbrück, J. Stuckert
Annals of Nuclear Energy 36, 1349
http://dx.doi.org/10.1016/j.anucene.2009.06.020

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
J. Stuckert, J.C. Birchley, M. Große, T.J. Haste, L. Sepold, M. Steinbrück
Annals of Nuclear Energy* 36, 183
http://dx.doi.org/10.1016/j.anucene.2008.11.024

Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear
Y. Liao, S. Güntay
Nuclear Engineering and Design 239, 1128
http://dx.doi.org/10.1016/j.nucengdes.2009.02.003

Separate-effect tests on zirconium cladding degradation in air ingress situations
C. Duriez, M. Steinbrück, D. Ohai, T. Meleg, J.C. Birchley, T.J. Haste
Nuclear Engineering and Design 239, 244
http://dx.doi.org/10.1016/j.nucengdes.2008.10.017

A Generalized Mean Temperature Difference Method For Thermal Design Of Heat Exchangers
M. Utamura, K. Nikitin, Y. Kato
Ijnest, 4(1), (2008)


Steam Condensing Liquid Co2 Boiling Heat Transfer In A Steam Condenser For A New Heat Recovery System
K. Nikitin, Y. Kato, T. Ishizuka
International Journal of Heat And Mass Transfer, 51(17/18), 4544-4550 (2008)


Uncertainty And Sensitivity Analysis Of The Loft L2-5 Test: Results Of The Bemuse Programme
De CréCy A., Bazin P., Glaeser H., Skorek T., Joucla J., Probst P., Fujioka K., Chung B.D., Oh D.Y., Kyncl M., Pernica R., Macek J., Meca R., Macian R., D’Auria F. Petruzzi A. Bater L., Perez M., Reventos F.
Nuclear Engineering and Des. (Issn 0029-5493), 238, 3561-3578 (2008)

X-Ray Absorption Spectra Of Hexagonal Ice And Liquid Water By All-Electron Gaussian And Augmented Plane Wave Calculations
M. Iannuzzi-Mauri
J. Chem. Phys. (Issn 0021-9606), 128, 204506-204506-12 (2008)


First-Principles Molecular Dynamics Study Of The Heterogeneous Reduction Of No2 On Soot Surfaces
Rodriguez-Fortea A., Iannuzzi Mauri M.
J. Phys. Chem C (Issn 1932-7447), 112, 19642-19648 (2008)


Modeling Bulk And Surface Pt Using The “Gaussian And Plane Wave” Density Functional Theory Formalism: Validation And Comparison To K-Point Plane Wave Calculations
G. Santarossa, A. Vargas, Mauri. Iannuzzi, Pignedoli. M, A. C, D. Passerone, A. Baiker
J. Chem. Phys. (Issn 0021-9606), 129, 234703-234703-12 (2008)


Chiral Recognition On Catalytic Surfaces: Theoretical Insight In A Biomimetic Heterogeneous Catalytic System
A. Vargas, G. Santarossa, Mauri. Iannuzzi, Baiker. M,
J. Phys. Chem C (Issn 1932-7447), 112, 10200-10208 (2008)

Effects of chlorine and sulphur on particle formation in wood combustion performed in a laboratory scale reactor
O. Sippula, T.M. Lind, J.K. Jokiniemi
Journal of Fuel 87, 2425
http://dx.doi.org/10.1016/j.fuel.2008.02.004

A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1
A. Rýdl
Nuclear Engineering and Design* 238, 2387
http://dx.doi.org/10.1016/j.nucengdes.2008.02.027

Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR
J.C. Birchley, T.J. Haste, M. Richner
Nuclear Engineering and Design 238, 2173
http://dx.doi.org/10.1016/j.nucengdes.2008.02.009

Validation of severe accident codes on the Phebus fission product tests in the framework of the PHEBEN-2 project
K. Müller, S. Dickinson, C. de Pascale, N. Girault, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuentes, I. Turcu, I. Ivanov, B. Toth, L.G. Horvath
Nuclear Technology 163, 209

Bwr Stability And Bifurcatio Analysis Using Reduced Order Models And System Codes: Identification Of A Subcritical Hop Bifurcation Using Ramona
A. Dokhane, D. Hennig, Rizwan-Uddin, R. Chawla
Annals of Nuclear Energy, Volume 34, Issue 10, October 2007, Pp 792-802 (2007)

Experimental Investigation On Bublbe Turbulent Diffusion In A Vertical Large-Diameter Pipe By Wire-Mesh Sensors And Correlation Techniques
A. Manera, H-M. Prasser, D. Lucas
Nuclear Technology, 158(2), 291-303 (2007)


Fine particle and trace element emissions from waste combustion - Comparison of fluidized bed and grate firing
T.M. Lind, J. Hokkinen, J.K. Jokiniemi
Fuel Processing Technology 88, 737
http://dx.doi.org/10.1016/j.fuproc.2007.03.004

Major challenges to modeling aerosol retention near a tube breach during steam generator tube rupture sequences
L.E. Herranz, C. Lopez del Pra, A. Dehbi
Nuclear Technology 158, 83

Benchmark study on fuel bundle degradation in the Phebus FPT3 test using the severe accident codes ATHLET-CD, ICARE2, and MELCOR
B. Toth, K. Müller, J.C. Birchley, H. Wada, C. Jamond, K. Trambauer
Nuclear Technology 157, 132

Retran-3d Analysis Of The Base Case And The Four Extreme Cases Of The Oecd/Nea Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington, H. Ferroukhi
Annals of Nuclear Energy 33, Pp 99-118 (2006)

Spatial And Model-Order Based Reactor Signal Analysis Methodolgy For Bwr Core Stability Evaluation
A. Dokhane, H. Ferroukhi, M.A. Zimmermann, C. Aguirre
Annals of Nuclear Energy, Volume 33, Issue 16, November 2006, Pp 1329-1338 (2006)

Modeling The Cabri High-Burnup Ria Test Cip0-1 Using An Extended Version Of The Falcon Code
A. Romano, H. Wallin, M.A. Zimmermann, R. Chawla
Nuclear Engineering and Des. (Issn 0029-5493), 236, 284-294 (2006)

Implications Of Alternative Strategies For Transitions To Sustainable Fuel Cycles
A. Romano, T. Boscher, P. Hejzlar, M. Kazimi, N. Todreas
Nuclear Sci. Engineering and (Issn 0029-5639), 154, 1-27 (2006)

Effect of chlorine and sulfur on fine particle formation in pilot-scale CFBC of biomass
T.M. Lind, E.L. Kauppinen, J. Hokkinen, J.K. Jokiniemi, M. Orjala, M. Aurela, R. Hillamo
Energy and Fuels 20, 61
http://dx.doi.org/10.1021/ef050122i

Electrostatic precipitator performance and trace element emissions from two Kraft recovery boilers
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, R. Hillamo, U. Makkonen, A. Raukola, J. Rintanen, K. Saviharju
Environmental Science & Technology 40, 584
http://dx.doi.org/10.1021/es0503027

MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
T.J. Haste, J.C. Birchley, E.G. Cazzoli, J. Vitazkova
Nuclear Engineering and Design 236, 1099
http://dx.doi.org/10.1002/j.nucengdes.2005.11.012

Semi-Analytical Bifurcation Analysis Of Two-Phase Flow In A Heated Channel
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Int. J. Bifurcation Chaos (Issn 0218-1274), 15, 2395-2409 (2005)


Review Of The Licensing Basis For Ria And Loca Transients In Light Of New Evidence On High Burnup Fuel Behavior
M. Zimmermann, Bart. A,
Chimia (Issn 0009-4293), 59, 950-956 (2005)


Open-Pore Organic Material for Retaining Radioactive I2 and CH3I
T. Hertzsch, C. Gervais, J. Hulliger, B.S. Jäckel, S. Güntay, H. Bruchertseifer, A. Neels
Advanced Functional Materials 16, 268
http://dx.doi.org/10.1002/adfm.200500245

Development of semi-automated system for preparation of Re-188 aqueous solutions of high and reproducible activity concentrations
B.S. Jäckel, R.C. Cripps, Güntay, H. Bruchertseifer
Applied Radiation and Isotopes 63, 299
http://dx.doi.org/10.1016/j.apradiso.2005.04.009

Iodine behaviour during a severe accident in a nuclear power plant
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Chimia 59, 957
http://dx.doi.org/10.2533/000942905777675453

Phebus-FP: Results and significance for plant safety in Switzerland
J.C. Birchley, T.J. Haste, H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Nuclear Engineering and Design 235, 1607
http://dx.doi.org/10.1016/j.nucengdes.2005.02.018

Steam generator tube rupture (SGTR) scenarios
A. Auvinen, J.K. Jokiniemi, A. Lahde, T. Routamo, P. Lundstrom, H. Tuomisto, J. Dienstbier, S. Güntay, D.J. Suckow, A. Dehbi, M. Slootman, L.E. Herranz, V. Peyres, J. Polo
Nuclear Engineering and Design 235, 457
http://dx.doi.org/10.1016/j.nucengdes.2004.08.060

European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE)
D. Magallon, A. Mailliat, J.M. Seiler, K. Athken, H. Sjovall, S. Dickinson, J. Jakab, L. Meyer, M. Buerger, K. Trambauer, L. Fickert, B.R. Sehgal, Z. Hozer, J. Bagues, F. Martin-Fuentes, R. Zeyen, A. Annunziato, M. El-Shanawany, S. Güntay, C. Tinkler, B. Turland, L.E. Herranz
Nuclear Engineering and Design 235, 309
http://dx.doi.org/10.1016/j.nucengdes.2004.08.042

On the radiolytic decomposition of colloidal silver iodide in aqueous suspension
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Nuclear Technology 150, 303

 

 

 

 

 

 

 

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Void Fraction And Critical Power Assessment Of Coretran-01/Vipre-02
Y. Aounallah
Nuclear Technol. (Issn 0029-5450), 145, 163-176 (2004)

Peach Bottom Bwr Turbine Trip Benchmark Analyses With Retran-3d And Coretran
W. Barten, H. Ferroukhi, P. Coddington
Nuclear Sci. Engineering and (Issn 0029-5639), 146, 306-324 (2004)

ARTIST: introduction and first results
S. Güntay, D.J. Suckow, A. Dehbi, R. Kapulla
Nuclear Engineering and Design 231, 109
http://dx.doi.org/10.1016/j.nucengdes.2004.02.012

The Analysis Of Pwr And Bwr Reactivity Transients With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Nuclear Technology, 142, 19-34 (2003)

Comparison Of Various Partial Light Water Reactor Core Loadings With Inert Matrix And Mixed-Oxide Fuel
U. Kasemeyer, Ch. Hellwig, J. Lebenhaft, R. Chawla
Journal of Nuclear Materials, 319, 142-153 (2003)

Assessment Of Retran-3d Boiling Models Against Experimental Subcooled Boiling Tube Data
R. Macian, P. Coddington, P. Stangroom
Nuclear Technology, Vol. 142, 47-63 (2003)

Interpretation Of Experimental Results From Moderate-Power In-Pile Testing Of A Pu-Er-Zr-Oxide Inert Matrix Fuel
Hellwig Ch., Kasemeyer U., Ledergerber G., Byung-Ho Lee, Young-Woo Lee, Chawla R.
Annals of Nuclear Energy 30, 287-299 (2003)

Planned Experimental Studies On Natural Circulation And Stability Performance Of Boiling Water Reactors In Four Experimental Facilities And First Results (Nacusp
De Kruijf W.J.M., Katelaar K.C.J, Avakian G., Gubernatis P., Caruge D., Manera A., Van Der Hagen T.H.J.J., Yadigaroglu G., Domenicus G., Rohde U., Prasser H.-M., Castrillo F., Huggenberger M., Hennig D., Munoz-Cobo J.L., Aguirre C.
Nuclear Engineering And Design, 221, 241-250 (2003)

Analysis of iodine species in aqueous solutions
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Analytical and Bioanalytical Chemistry 375, 1107
http://dx.doi.org/10.1007/s00216-003-1779-3

Fission product iodine release and retention in nuclear reactor accidents - experimental programme at PSI
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Czechoslovak Journal of Physics 53, 611
http://dx.doi.org/10.1007/s10582-003-0079-7

Electrostatic precipitator collection efficiency and trace element emissions from co-combustion of biomass and recovered fuel in fluidized-bed combustion
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, S. Saarikoski, R. Hillamo
Environmental Science & Technology 37, 2842
http://dx.doi.org/10.1021/es026314z

Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project
A.V. Jones, S. Dickinson, C. de Pascale, N. Hanniet, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, J.C. Birchley, S. Paci, F. Martin-Fuentes
Nuclear Engineering and Design 221, 225
http://dx.doi.org/10.1016/S0029-5493(02)00340-0

Core loss during a severe accident (COLOSS)
B. Adroguer, P. Chatelard, J.P. van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 221, 55
http://dx.doi.org/10.1016/S0029-5493(02)00344-8

Analysis And Sensitivity Studies Of Postulated Sb-Locas In The MüHleberg (Kkm) Bwr/4 By Trac-Bf1
G. Analytis, Coddington. Th,
Annals of Nuclear Energy, 29, 1525-1549 (2002)

A Novel Auto-Correlation Function Method For The Determination Of The Decay Ratio In Bwr Stability Analysis
K. Behringer, D. Hennig
Annals of Nuclear Energy, 29, 1483-1504 (2002)

A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Nuclear Engineering And Design, 215, 199-216

Application And In-Depth Assessment Of Retran-3d For Best Estimate Analysis Of Nuclear Power Plant Transients
P. Coddington, R. Macian, M. Zimmermann, Chawla. A,
Journal of Nuclear Science And Technology, 39-9, 972-985 (2002)

Simulation And Analysis Of Experimental Blow Down And Small-Break Loss-Of-Coolant Scenarios With Retran-3d
R. Macian, P. Coddington
Nuclear Technology, Vol. 139, 185-204 (2002)

A Nodal Modal Method For The Neutron Diffusion Equation. Application To Bwr Stability Analysis
R. Miro, D. Ginestar, G. Verdu, D. Hennig
Annals of Nuclear Energy, 29, 1171-1194 (2002)

On The Feasibility Of Ads-Representative Integral Experiments Using Limited Amounts Of Low-Enriched U-Fuel
S. Pelloni, R. Chawla
Journal of Nuclear Science And Technology, Supplement 2, 1224-1227 (2002)

Data Sensitivity Of Design Calculations For High Conversion D2o Reactors
S. Pelloni, H. Hager, O. Joneja, Chawla. P,
Journal of Nuclear Science And Technology, Supplement 2, 880-883 (2002)

The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 Bwr
G. Analytis, Hennig. Th, H. D, K. Karlsson,
Nuclear Engineering And Design, Vol. 205, Pp. 91-105, 2001.

Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, J. Meseth, S. Güntay, D.J. Suckow, J.L. Jimenez, L.E. Herranz, V. Peyres, G.F. De Santi, A. Krasenbrink, M. Valisi, L. Mazzochi
Nuclear Engineering and Design 209, 253
http://dx.doi.org/10.1016/S0029-5493(01)00408-3

Aerosol retention in low-subcooling pools under realistic accident conditions
A. Dehbi, D.J. Suckow, S. Güntay
Nuclear Engineering and Design 203, 229
http://dx.doi.org/10.1016/S0029-5493(00)00343-5

 

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A Study Of Boiling Water Reactor Stability Behaviour
D. Hennig
Nuclear Technology, Vol. 126, Pp 10-31, (1999)

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Nuclear Technology, Vol. 128, Pp 139-152, (1999)

Evaluation Of The Slip Option In Retran-3d
D. Maier, P. Coddington
Nuclear Technology, Vol. 128, Pp 153-168, (1999)

Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Nuclear Technology, Vol. 128, Pp 225-232, (1999)

Field study on ash behavior during circulating fluidized-bed combustion of biomass. 2. Ash deposition and alkali vapor condensation
T. Valmari, T.M. Lind, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Energy & Fuels 13, 390
http://dx.doi.org/10.1021/ef9800866

Field study on ash behavior during circulating fluidized-bed combustion of biomass. 1. Ash formation
T. Valmari, T.M. Lind, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Energy & Fuels 13, 379
http://dx.doi.org/10.1021/ef980085d

Volatilization of the heavy metals during circulating fluidized bed combustion of forest residue
T.M. Lind, T. Valmari, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Environmental Science & Technology 33, 496
http://dx.doi.org/10.1021/es9802596

Core melt down and vessel failure: a coupled problem
G. Duijvestijn, J.C. Birchley
Nuclear Engineering and Design 191, 17
http://dx.doi.org/10.1016/S0029-5493(99)00050-3

Prediction of thermoplastic failure of a reactor pressure vessel under a postulated core melt accident
G. Duijvestijn, J.C. Birchley, K. Reichlin
Computers & Structures 64, 1239
http://dx.doi.org/10.1016/S0045-7949(97)00032-1

A model for the performance of a vertical tube condenser in the presence of noncondensable gases
A. Dehbi, S. Güntay
Nuclear Engineering and Design 177, 41
http://dx.doi.org/10.1016/S0029-5493(97)00184-2

CORVIS. Investigation of light water reactor lower head failure modes
S. Brosi, G. Duijvestijn, H. Hirschmann, B.S. Jäckel, K. Nakada, J.A. Patorski, R. Rösel, H.P. Seifert, P. Tipping
Nuclear Engineering and Design 168, 77
http://dx.doi.org/10.1016/S0029-5493(96)00008-8

Ash vaporization in circulating fluidized bed coal combustion
T.M. Lind, E.I. Kauppinen, W. Maenhaut, A. Shah, F. Huggins
Aerosol Science and Technology 24, 135
http://dx.doi.org/10.1080/02786829608965359

Fuel-Temperature Coefficient For Boiling Water Reactor Transient Calculations: Its Dependence On Reactor Conditions
J.M. Kallfelz, L.A. Belblidia, P. Grimm
Nuclear Science And Engineering 121 (1995), 301-311

CORVIS - Researching Reactor Pressure-Vessel Melt Through
H. Hirschmann, J.P. Hosemann, B.S. Jäckel
Nuclear Engineering International 40, 34

Cross-Sections of Proton-Induced Nuclear-Reactions on Enriched Cd-111 and Cd-112 for the Production of In-111 for use in Nuclear-Medicine
F. Tarkanyi, F. Szelecsenyi, P. Kopecký, T. Molnar, L. Ando, P. Mikecz, G. Toth, A. Rýdl
Applied Radiation and Isotopes 45, 239
http://dx.doi.org/10.1016/0969-8043(94)90018-3

Study of Size-Fractionated Coal-Combustion Aerosols using Instrumental Neutron-Activation Analysis
W. Maenhaut, E.I. Kauppinen, T.M. Lind
Journal of Radioanalytical and Nuclear Chemistry - Articles 167, 259
http://dx.doi.org/10.1007/BF02037185

Analysis of Size-Fractionated Coal Combustion Aerosols by PIXE and other Analytical Techniques
W. Maenhaut, O. Royset, M. Vadset, E.I. Kauppinen, T.M. Lind
Nuclear Instruments and Methods in Physics Research Section B - Beam Interactions with Materials and Atoms 75, 266
http://dx.doi.org/10.1016/0168-583X(93)95656-P

Evaluation of Neutral Dialkoxy Dithiophosphate Complexes of Thallium-201 as Myocardial Perfusion Tracers
P. Kopecký, A. Rýdl, B. Kopecká, P. Švihovcová, K. Bakos
European Journal of Nuclear Medicine 18, 669

Aerosols from Circulating Fluidized-Bed Coal Combustion
E.I. Kauppinen, T.M. Lind, J.J. Eskelinen, J.K. Jokiniemi, W. Maenhaut, O. Royset, M. Vadset, H. Vilokki, R. Kuivalainen
Journal of Aerosol Science 22, 467
http://dx.doi.org/10.1016/S0021-8502(05)80139-9

Mass and Charge Flow in the reaction 7.1 MeV/u Au-197 + Cu-63
B.S. Jäckel, A. Rox, B.A. Esterlund, W. Westmaier, M. Knaack, P. Patzelt
Zeitschrift für Physik A-Hadrons and Nuclei 339, 475
http://dx.doi.org/10.1007/BF01288431

Dynamic Contributions to Symmetric Fragmentation Processes
H. Schulte, B.S. Jäckel, B.A. Esterlund, M. Knaack, W. Westmaier, A. Rox, P. Patzelt
Physics Letters B 232, 37
http://dx.doi.org/10.1016/0370-2693(89)90554-6

On the Photopeak Efficiency of Germanium Gamma-Ray Detectors
B.S. Jäckel, W. Westmaier, P. Patzelt
Nuclear Instruments & Methods in Physics Research Section A - Accelerators Spectrometers Detectors and associated Equipment 261, 543
http://dx.doi.org/10.1016/0168-9002(87)90367-6

Studies on the Biological Half-Life of Cesium in Roe Deer
D. Molzahn, J. van Aarle, A. Merklin, B.S. Jäckel, W. Westmaier, P. Patzelt
Zeitschrift für Jagdwissenschaft 33, 89
http://dx.doi.org/10.1007/BF02241758

Transient Evaporation and Combustion of a Composite Water-Oil Droplet
J.C. Birchley, N. Riley
Combustion and Flame* 29, 145
http://dx.doi.org/10.1016/0010-2180(77)90104-3

Droplet Combustion in a Stream of Oxidant
J.C. Birchley
Mathematical Physical and Engineering Sciences 347, 195
http://dx.doi.org/10.1098/rspa.1975.0205

Droplet Combustion in a Stream of Oxidant
J.C. Birchley
Mathematical Physical and Engineering Sciences 347, 195
http://dx.doi.org/10.1098/rspa.1975.0205

 

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