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Laboratory for Reactor Physics and Thermal-Hydraulics

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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:
 

  • Nuclear Engineering and Technology
  • Nuclear Engineering and Design
  • Annals of Nuclear Energy
  • EPJ Nuclear Scientific Technologies
  • Neural Computing and Applications
  • Progress in Nuclear Energy
  • Experimental Thermal and Fluid Science
  • Physical Review Letters

2023

  • 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
  • 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
  • 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
  • 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
  • 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
  • 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
  • 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
  • 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
  • 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
    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
  • 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
  • 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 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
  • 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
  • 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
  • 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
  • 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

 

>>Back to top

2022

  • 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
  • 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. 2022. https://doi.org/10.1080/00295639.2022.2140577
    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
    Nuclear Technology. 2022. https://doi.org/10.1080/00295450.2022.2133505
    DORA PSI
  • Martinez-Quiroga V, Szogradi M, Schollenberger S, Sanchez-Perea M, Sandberg N, Zhongyun J, et al.
    OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
    Nuclear Engineering and Design. 2022; 389: 111632 (20 pp.). https://doi.org/10.1016/j.nucengdes.2021.111632
    DORA PSI
  • Moreno-Soto J, Valenta S, Berthoumieux E, Chebboubi A, Diakaki M, Dridi W, et al.
    Constraints on the dipole photon strength for the odd uranium isotopes
    Physical Review C: Nuclear Physics. 2022; 105(2): 024618 (14 pp.). https://doi.org/10.1103/PhysRevC.105.024618
    DORA PSI
  • Nichenko S, Kalilainen J, Lind T
    MSR simulation with cGEMS: fission product release and aerosol formation
    Journal of Nuclear Engineering. 2022; 3(1): 105-116. https://doi.org/10.3390/jne3010006
    DORA PSI
  • Nikitin K, Clifford I, Dokhane A, Ferroukhi H
    Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
    Nuclear Engineering and Design. 2022; 389: 111649 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.111649
    DORA PSI
  • Pakari OV, Lamirand V, Mager T, Frajtag P, Pautz A
    High accuracy measurement of the prompt neutron decay constant in CROCUS using gamma noise and bootstrapped uncertainties
    Annals of Nuclear Energy. 2022; 170: 109011 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109011
    DORA PSI
  • Paladino D, Kapulla R, Paranjape S, Suter S, Andreani M
    PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena
    Nuclear Engineering and Design. 2022; 392: 111777 (18 pp.). https://doi.org/10.1016/j.nucengdes.2022.111777
    DORA PSI
  • Paladino D, Paranjape S, Mignot G, Kapulla R
    Parametric study highlighting cooler and spray activation on the transient mixing of a three-gas composition in the PANDA facility
    Progress in Nuclear Energy. 2022; 150: 104283 (9 pp.). https://doi.org/10.1016/j.pnucene.2022.104283
    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. 2022. https://doi.org/10.1016/j.proci.2022.08.034
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs
    Nuclear Engineering and Design. 2022; 398: 111946 (16 pp.). https://doi.org/10.1016/j.nucengdes.2022.111946
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data
    Annals of Nuclear Energy. 2022; 178: 109385 (34 pp.). https://doi.org/10.1016/j.anucene.2022.109385
    DORA PSI
  • Papaoikonomou A, Wingate J, Verma V, Durrant A, Ioannou G, Papagiannis T, et al.
    Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements
    Annals of Nuclear Energy. 2022; 178: 109373 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109373
    DORA PSI
  • Pelloni S, Rochman D
    Adjustment of JEFF-3.3 data for U-235 and Pu-239 in the fast, non-resonant energy range
    Annals of Nuclear Energy. 2022; 177: 109296 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109296
    DORA PSI
  • Perret G, Wicaksono D, Clifford ID, Ferroukhi H
    Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
    Nuclear Technology. 2022; 208(4): 711-722. https://doi.org/10.1080/00295450.2021.1936879
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Muñoz A, Vazquez Antolin M, Berrios Torres M, et al.
    Analysis of ENRESA BWR samples: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2022; 8: 9 (16 pp.). https://doi.org/10.1051/epjn/2022007
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Koning A, Sublet J-C
    Impact of H in H2O thermal scattering data on criticality calculation: uncertainty and adjustment
    EPJ Nuclear Sciences and Technologies. 2022; 8: 3 (7 pp.). https://doi.org/10.1051/epjn/2021028
    DORA PSI
  • Scolaro A, Fiorina C, Clifford I, Pautz A
    Development of a semi-implicit contact methodology for finite volume stress solvers
    International Journal for Numerical Methods in Engineering. 2022; 123(2): 309-338. https://doi.org/10.1002/nme.6857
    DORA PSI
  • Scolaro A, Van Uffelen P, Schubert A, Fiorina C, Brunetto E, Clifford I, et al.
    Towards coupling conventional with high-fidelity fuel behavior analysis tools
    Progress in Nuclear Energy. 2022; 152: 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
    DORA PSI
  • Shama A, Rochman D, Caruso S, Pautz A
    Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
    Annals of Nuclear Energy. 2022; 165: 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758
    DORA PSI
  • Vidal-Ferràndiz A, Ginestar D, Carreño A, Verdú G, Dokhane A, Verma V, et al.
    Modelling and simulations of reactor neutron noise induced by mechanical vibrations
    Annals of Nuclear Energy. 2022; 177: 109300 (21 pp.). https://doi.org/10.1016/j.anucene.2022.109300
    DORA PSI
  • Ványi AS, Hursin M, Czifrus S
    Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors
    Annals of Nuclear Energy. 2022; 174: 109147 (11 pp.). https://doi.org/10.1016/j.anucene.2022.109147
    DORA PSI
  • Wei Z, Ničeno B, Puragliesi R, Fogliatto E
    Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
    Nuclear Engineering and Technology. 2022; 54(11): 4359-4372. https://doi.org/10.1016/j.net.2022.07.009
    DORA PSI
  • Welker Z, Manera A, Petrov V, Balestra P
    An experimental and theoretical examination of air ingress rates during small- and medium-break air ingress accidents
    Nuclear Technology. 2022: (15 pp.). https://doi.org/10.1080/00295450.2022.2134673
    DORA PSI
  • Yoon HJ, Alyammahi N, Al-Yahia OS, Leung R
    Validation of RELAP5 MOD3.3 for 1% reactor pressure vessel top head break loss of coolant accident via the ATLAS facility
    Nuclear Engineering and Design. 2022; 400: 112054 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.112054
    DORA PSI
  • Yum S, Hursin M, Vasiliev A, Vinai P, Mylonakis AG, Demazière C, et al.
    Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
    Annals of Nuclear Energy. 2022; 174: 109157 (13 pp.). https://doi.org/10.1016/j.anucene.2022.109157
    DORA PSI

 

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2021

  • Adams R, Günther C, Höflich N, Pooth O
    A 2D pixelated stilbene scintillator detector array for simultaneous radiography with fast neutrons and gammas
    Journal of Instrumentation. 2021; 16(2): P02021 (21 pp.). https://doi.org/10.1088/1748-0221/16/02/P02021
    DORA PSI
  • Amaducci S, Colonna N, Cosentino L, Cristallo S, Finocchiaro P, Krtička M, et al.
    First results of the 140Ce(n,ү)141Ce cross-section measurement at n_TOF
    Universe. 2021; 7(6): 200 (11 pp.). https://doi.org/10.3390/UNIVERSE7060200
    DORA PSI
  • Babiano-Suárez V, Lerendegui-Marco J, Balibrea-Correa J, Caballero L, Calvo D, Ladarescu I, et al.
    Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques
    European Physical Journal A: Hadrons and Nuclei. 2021; 57(6): 197 (17 pp.). https://doi.org/10.1140/epja/s10050-021-00507-7
    DORA PSI
  • Breitenmoser D, Papadopoulos P, Lind T, Prasser H-M
    Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection
    International Journal of Multiphase Flow. 2021; 142: 103694 (15 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103694
    DORA PSI
  • Choi YJ, Kam DH, Padopoulos P, Lind T, Jeong YH
    Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
    Nuclear Engineering and Technology. 2021; 53: 1756-1768. https://doi.org/10.1016/j.net.2020.11.024
    DORA PSI
  • Clifford I, Ferroukhi H
    Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE
    Nuclear Engineering and Design. 2021; 383: 111446 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111446
    DORA PSI
  • Dokhane A, Hursin M, Vasiliev A, Rochman D, Ferroukhi H
    Recent developments in PSI BEPU analysis for SPERT-III RIA transient: ND uncertainty breakdown and kinetic parameters uncertainty assessment
    Nuclear Engineering and Design. 2021; 382: 111378 (14 pp.). https://doi.org/10.1016/j.nucengdes.2021.111378
    DORA PSI
  • Doll U, Barro C, Todino M, Boulouchos K
    Impact of a split injection strategy on mixing, ignition and combustion behavior in premixed charge compression ignition combustion
    Fuel. 2021; 294: 120511 (14 pp.). https://doi.org/10.1016/j.fuel.2021.120511
    DORA PSI
  • Falsetti C, Kapulla R, Paranjape S, Paladino D
    Thermal radiation, its effect on thermocouple measurements in the PANDA facility and how to compensate it
    Nuclear Engineering and Design. 2021; 375: 111077 (9 pp.). https://doi.org/10.1016/j.nucengdes.2021.111077
    DORA PSI
  • Frankl M, Hursin M, Rochman D, Vasiliev A, Ferroukhi H
    Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal
    Applied Sciences. 2021; 11(14): 6499 (19 pp.). https://doi.org/10.3390/app11146499
    DORA PSI
  • Kapulla R, Manohar KH, Paranjape S, Paladino D
    Self-similarity for statistical properties in low-order representations of a large-scale turbulent round jet based on the proper orthogonal decomposition
    Experimental Thermal and Fluid Science. 2021; 123: 110320 (16 pp.). https://doi.org/10.1016/j.expthermflusci.2020.110320
    DORA PSI
  • Khvostov G, Gorzel A
    FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
    Nuclear Engineering and Technology. 2021; 53(11): 3741-3758. https://doi.org/10.1016/j.net.2021.06.001
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
    Journal of Nuclear Materials. 2021; 555: 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
    DORA PSI
  • Kromer H, Adams R, Prasser H-M
    Development, design, and testing of a microwave-driven compact rotating-target D-D fast neutron generator for imaging applications
    Applied Radiation and Isotopes. 2021; 174: 109715 (14 pp.). https://doi.org/10.1016/j.apradiso.2021.109715
    DORA PSI
  • Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, 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 3
    Nuclear Engineering and Design. 2021; 376: 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138
    DORA PSI
  • Nichenko S, Kalilainen J, Fernandez Moguel L, Lind T
    Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
    Annals of Nuclear Energy. 2021; 152: 107972 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107972
    DORA PSI
  • Pakari O, Mager T, Lamirand V, Frajtag P, Pautz A
    Delayed gamma fraction determination in the zero power reactor CROCUS
    EPJ Nuclear Sciences and Technologies. 2021; 7: 16 (6 pp.). https://doi.org/10.1051/epjn/2021015
    DORA PSI
  • Pelloni S, Rochman D
    Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
    Annals of Nuclear Energy. 2021; 163: 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
    DORA PSI
  • Pázsit I, Torres LA, Hursin M, Nylén H, Dykin V, Montalvo C
    Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
    Progress in Nuclear Energy. 2021; 138: 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
    DORA PSI
  • Pérot B, Carasco C, Eléon C, Bernard S, Sardet A, El Kanawati W, et al.
    Sea container inspection with tagged neutrons
    EPJ Nuclear Sciences and Technologies. 2021; 7: 6 (37 pp.). https://doi.org/10.1051/epjn/2021004
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M
    Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 18 (24 pp.). https://doi.org/10.1051/epjn/2021017
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M
    Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
    Annals of Nuclear Energy. 2021; 160: 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M, Ichou R, Taforeau J, et al.
    Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 14 (24 pp.). https://doi.org/10.1051/epjn/2021013
    DORA PSI
  • Rochman DA, Bauge E
    Fission yields and cross sections: correlated or not?
    EPJ Nuclear Sciences and Technologies. 2021; 7: 5 (9 pp.). https://doi.org/10.1051/epjn/2021005
    DORA PSI
  • Rochman D, Hursin M, Vasiliev A, Ferroukhi H
    Impact of H in H2O thermal scattering data on depletion calculation: k∞, nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 24 (8 pp.). https://doi.org/10.1051/epjn/2021027
    DORA PSI
  • Rochman D, Shama A, Pudollek S, Caruso S, Pautz A
    Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
    Nuclear Engineering and Technology. 2021; 53(9): 2816-2829. https://doi.org/10.1016/j.net.2021.03.013
    DORA PSI
  • Schnabel G, Sjöstrand H, Hansson J, Rochman D, Koning A, Capote R
    Conception and software implementation of a nuclear data evaluation pipeline
    Nuclear Data Sheets. 2021; 173: 239-284. https://doi.org/10.1016/j.nds.2021.04.007
    DORA PSI
  • Scolaro A, Van Uffelen P, Fiorina C, Schubert A, Clifford I, Pautz A
    Investigation on the effect of eccentricity for fuel disc irradiation tests
    Nuclear Engineering and Technology. 2021; 53(5): 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
    DORA PSI
  • Siefman D, Hursin M, Schnabel G, Sjöstrand H
    Development and application of marginal likelihood optimization for integral parameter adjustment
    Annals of Nuclear Energy. 2021; 159: 108255 (10 pp.). https://doi.org/10.1016/j.anucene.2021.108255
    DORA PSI
  • Skolik K, Allison C, Hohorst J, Malicki M, Perez-Ferragut M, Pieńkowski L, et al.
    Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
    Progress in Nuclear Energy. 2021; 134: 103648 (15 pp.). https://doi.org/10.1016/j.pnucene.2021.103648
    DORA PSI
  • Sobes V, de Saint Jean C, Rochman D, Cabellos O, Holcomb A, Bauge E, et al.
    WPEC Subgroup 44 computational inter-comparison exercise on correlations in nuclear data libraries
    Annals of Nuclear Energy. 2021; 164: 108605 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108605
    DORA PSI
  • Solans V, Rochman D, Brazell C, Vasiliev A, Ferroukhi H, Pautz A
    Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
    Neural Computing & Applications. 2021; 33: 16627-16639. https://doi.org/10.1007/s00521-021-06258-2
    DORA PSI
  • Soubelet B, Adams R, Prasser H-M
    Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator
    Radiation Physics and Chemistry. 2021; 181: 109296 (11 pp.). https://doi.org/10.1016/j.radphyschem.2020.109296
    DORA PSI
  • Stuckert J, Steinbrueck M, Kalilainen J, Lind T, Birchley J
    Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
    Nuclear Engineering and Design. 2021; 379: 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267
    DORA PSI
  • Torres Delgado LA, Verma V, Montalvo C, Dokhane A, García-Berrocal A
    Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
    Nuclear Engineering and Design. 2021; 373: 111017 (18 pp.). https://doi.org/10.1016/j.nucengdes.2020.111017
    DORA PSI
  • Verma V, Chionis D, Dokhane A, Ferroukhi H
    Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
    Annals of Nuclear Energy. 2021; 157: 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
    DORA PSI
  • Ványi AS, Babcsány B, Böröczki ZI, Horváth A, Hursin M, Szieberth M, et al.
    Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
    Annals of Nuclear Energy. 2021; 155: 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
    DORA PSI
  • Weilenmann M, Doll U, Bombach R, Blondé A, Ebi D, Xiong Y, et al.
    Linear and nonlinear entropy-wave response of technically-premixed jet-flames-array and swirled flame to acoustic forcing
    Proceedings of the Combustion Institute. 2021; 38(4): 6135-6143. https://doi.org/10.1016/j.proci.2020.06.233
    DORA PSI

 

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2020

  • 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
    Annals of Nuclear Energy. 2020; 139: 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
    DORA PSI
  • Andreani M, Kapulla R, Kelm S, Paladino D, Paranjape S
    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
    Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021110 (18 pp.). https://doi.org/10.1115/1.4046296
    DORA PSI
  • Andreani M, Paranjape S
    Gas mixing caused by interacting heat sources. Part ii: modelling
    Nuclear Engineering and Design. 2020; 370: 110887 (16 pp.). https://doi.org/10.1016/j.nucengdes.2020.110887
    DORA PSI
  • Betschart T, Lind T, Prasser H-M
    Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
    Nuclear Engineering and Design. 2020; 366: 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
    DORA PSI
  • Chionis D, Dokhane A, Belblidia L, Ferroukhi H, Girardin G, Pautz A
    Development and verification of a methodology for neutron noise response to fuel assembly vibrations
    Annals of Nuclear Energy. 2020; 147: 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
    DORA PSI
  • Fiorina C, Scolaro A, Siefman D, Hursin M, Pautz A
    Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
    Journal of Nuclear Engineering. 2020; 1(1): 54-62. https://doi.org/10.3390/jne1010005
    DORA PSI
  • Guerrero C, Lerendegui-Marco J, Paul M, Tessler M, Heinitz S, Domingo-Pardo C, et al.
    Neutron capture on the s-process branching point 171Tm via time-of-flight and activation
    Physical Review Letters. 2020; 125(14): 142701 (8 pp.). https://doi.org/10.1103/PhysRevLett.125.142701
    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 2 - results of severe accident analyses for Unit 1
    Nuclear Engineering and Design. 2020; 369: 110849 (7 pp.). https://doi.org/10.1016/j.nucengdes.2020.110849
    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 using neutron noise techniques
    Nuclear Technology. 2020; 206(10): 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
    DORA PSI
  • Hursin M, Pelloni S, Vasiliev A, Ferroukhi H
    Treatment of the implicit effect in Shark-X
    Annals of Nuclear Energy. 2020; 138: 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
    DORA PSI
  • Jäckel BS, Steiner P, Klügel J-U
    Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
    Nuclear Engineering and Design. 2020; 370: 110839 (6 pp.). https://doi.org/10.1016/j.nucengdes.2020.110839
    DORA PSI
  • Kalilainen J, Nichenko S, Krepel J
    Evaporation of materials from the molten salt reactor fuel under elevated temperatures
    Journal of Nuclear Materials. 2020; 533: 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
    DORA PSI
  • Khvostov G
    Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
    Nuclear Engineering and Technology. 2020; 52(12): 2887-2900. https://doi.org/10.1016/j.net.2020.05.015
    DORA PSI
  • Khvostov G
    Analytical criteria for fuel fragmentation and burst FGR during a LOCA
    Nuclear Engineering and Technology. 2020; 52(10): 2402-2409. https://doi.org/10.1016/j.net.2020.03.009
    DORA PSI
  • Khvostov G
    Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
    Nuclear Engineering and Technology. 2020; 52(1): 135-147. https://doi.org/10.1016/j.net.2019.07.010
    DORA PSI
  • Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D
    Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
    Annals of Nuclear Energy. 2020; 136: 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
    Kerntechnik. 2020; 85(6): 419-425. https://doi.org/10.3139/124.200072
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Uncertainty propagation based on correlated sampling technique for nuclear data applications
    EPJ Nuclear Sciences and Technologies. 2020; 6: 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
    EPJ Nuclear Sciences and Technologies. 2020; 6: 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
    DORA PSI
  • Lind T, Campbell S, Herranz LE, Kissane M, Song JH
    A summary of fission-product-transport phenomena during SGTR severe accidents
    Nuclear Engineering and Design. 2020; 363: 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
    DORA PSI
  • Mala P, Pautz A
    Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
    Nuclear Engineering and Technology. 2020; 52(11): 2431-2441. https://doi.org/10.1016/j.net.2020.04.022
    DORA PSI
  • Mazzone A, Cristallo S, Aberle O, Alaerts G, Alcayne V, Amaducci S, et al.
    Measurement of the 154Gd(n,γ) cross section and its astrophysical implications
    Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2020; 804: 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
    DORA PSI
  • Mora DF, Costa Garrido O, Mukin R, Niffenegger M
    Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
    Engineering Fracture Mechanics. 2020; 238: 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
    DORA PSI
  • 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
    Annals of Nuclear Energy. 2020; 137: 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
    DORA PSI
  • Nakayoshi A, Rempe JL, Barrachin M, Bottomley D, Jacquemain D, Journeau C, et al.
    Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
    Nuclear Engineering and Design. 2020; 369: 110857 (15 pp.). https://doi.org/10.1016/j.nucengdes.2020.110857
    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
    Nuclear Science and Engineering. 2020; 194(11): 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Gas mixing caused by interacting heat sources PART I: experiments
    Nuclear Engineering and Design. 2020; 370: 110914 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110914
    DORA PSI
  • Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyama Y, Gauntt R, et al.
    Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
    Nuclear Technology. 2020; 206(9): 1449-1463. https://doi.org/10.1080/00295450.2020.1724731
    DORA PSI
  • Pelloni S, Rochman D
    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
    DORA PSI
  • Plompen AJM, Cabellos O, De Saint Jean C, Fleming M, Algora A, Angelone M, et al.
    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
    DORA PSI
  • Puragliesi R
    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
    DORA PSI
  • 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
     

    Annals of Nuclear Energy. 2020; 148: 107706 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107706
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    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 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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2019

  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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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2018

  • Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
    Main results of the European PASSAM project on severe accident source term mitigation
    Annals of Nuclear Energy. 2018; 116: 42-56. https://doi.org/10.1016/j.anucene.2018.02.024
    DORA PSI
  • Andreani M, Paladino D, Papini D
    Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
    Nuclear Engineering and Design. 2018; 339: 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
    DORA PSI
  • Bauge E, Rochman DA
    Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
    EPJ Nuclear Sciences and Technologies. 2018; 4: 35 (6 pp.). https://doi.org/10.1051/epjn/2018011
    DORA PSI
  • Beghi I, Lind T, Prasser H-M
    Experimental studies on retention of iodine in a wet scrubber
    Nuclear Engineering and Design. 2018; 326: 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
    DORA PSI
  • Bousbia Salah A, Ceuca SC, Puragliesi R, Mukin R, Grahn A, Kliem S, et al.
    Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
    Nuclear Technology. 2018; 203(3): 293-314. https://doi.org/10.1080/00295450.2018.1461517
    DORA PSI
  • Brown DA, Chadwick MB, Capote R, Kahler AC, Trkov A, Herman MW, et al.
    ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data
    Nuclear Data Sheets. 2018; 148: 1-142. https://doi.org/10.1016/j.nds.2018.02.001
    DORA PSI
  • Clifford I, Pecchia M, Puragliesi R, Vasiliev A, Ferroukhi H
    On the characteristics of the flow and heat transfer in the core bypass region of a PWR
    Nuclear Engineering and Design. 2018; 330: 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
    DORA PSI
  • Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
    Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
    Annals of Nuclear Energy. 2018; 120: 880-887. https://doi.org/10.1016/j.anucene.2018.06.043
    DORA PSI
  • Cozzo C, Rahman S
    SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
    Progress in Nuclear Energy. 2018; 106: 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
    DORA PSI
  • Dokhane A, Grandi G, Vasiliev A, Rochman D, Ferroukhi H
    Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
    Annals of Nuclear Energy. 2018; 118: 178-184. https://doi.org/10.1016/j.anucene.2018.04.022
    DORA PSI
  • Dupont J, Mignot G, Paladino D, Prasser H-M
    Mid wave infrared thermography of water films in condensing and evaporating environments
    Nuclear Engineering and Design. 2018; 336: 80-89. https://doi.org/10.1016/j.nucengdes.2017.06.027
    DORA PSI
  • Dzysiuk N, Koning AJ, Rochman D, Fischer U
    Improving activation cross sections for fusion applications
    Fusion Science and Technology. 2018; 73(1): 13-24. https://doi.org/10.1080/15361055.2017.1372682
    DORA PSI
  • Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
    The role of nuclear data for fusion nuclear technology
    Fusion Engineering and Design. 2018; 136: 162-167. https://doi.org/10.1016/j.fusengdes.2018.01.036
    DORA PSI
  • 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: analysis of the PPOOLEX and PANDA experiments
    Nuclear Engineering and Design. 2018; 337: 300-316. https://doi.org/10.1016/j.nucengdes.2018.07.004
    DORA PSI
  • Gouëllo M, Kalilainen J, Kärkelä T, Auvinen A
    Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
    Nuclear Materials and Energy. 2018; 17: 259-268. https://doi.org/10.1016/j.nme.2018.11.011
    DORA PSI
  • Halouane Y, Dehbi A
    CFD simulation of hydrogen mitigation by a passive autocatalytic recombiner
    Nuclear Engineering and Design. 2018; 330: 488-496. https://doi.org/10.1016/j.nucengdes.2018.01.018
    DORA PSI
  • Hursin M, Weiss C, Frajtag P, Lamirand V, Perret G, Kavrigin P, et al.
    Testing of a sCVD diamond detection system in the CROCUS reactor
    European Physical Journal A: Hadrons and Nuclei. 2018; 54(5): 82 (11 pp.). https://doi.org/10.1140/epja/i2018-12519-1
    DORA PSI
  • Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A
    Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
    Annals of Nuclear Energy. 2018; 111: 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
    DORA PSI
  • Kapulla R, Mignot G, Paranjape S, Andreani M, Paladino D
    Large scale experiments representing a containment natural circulation loop during an accident scenario
    Science and Technology of Nuclear Installations. 2018; 2018: 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
    DORA PSI
  • Kapulla R, Uong D, Zimmer C, Paladino D
    PIV measurements in the vicinity of a steam sparger in the PANDA facility
    Nuclear Engineering and Design. 2018; 336: 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
    DORA PSI
  • Khvostov G
    Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
    Nuclear Engineering and Technology. 2018; 50(7): 1190-1197. https://doi.org/10.1016/j.net.2018.07.003
    DORA PSI
  • Khvostov G
    Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
    Nuclear Engineering and Design. 2018; 328: 36-57. https://doi.org/10.1016/j.nucengdes.2017.12.028
    DORA PSI
  • Kim H, Dehbi A, Kalilainen J
    Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
    Atmospheric Environment. 2018; 186: 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037
    DORA PSI
  • Marelli E, Villevieille C, Park S, Hérault N, Marino C
    Co-Free P2–Na0.67Mn0.6Fe0.25Al0.15O2 as promising cathode material for sodium-ion batteries
    ACS Applied Energy Materials. 2018; 1(11): 5960-5967. https://doi.org/10.1021/acsaem.8b01015
    DORA PSI
  • Mignot G, Dupont J, Paranjape S, Ouldrebai H, Bissels W-M, Paladino D, et al.
    Measurement of liquid films thickness in a condensing and re-evaporating environment using attenuation of near infrared light
    Nuclear Engineering and Design. 2018; 336: 64-73. https://doi.org/10.1016/j.nucengdes.2017.06.023
    DORA PSI
  • Mukin R, Clifford I, Zerkak O, Ferroukhi H
    Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
    Nuclear Engineering and Technology. 2018; 50(3): 356-367. https://doi.org/10.1016/j.net.2017.12.005
    DORA PSI
  • Mukin R, Puragliesi R, Pecchia M, Seidl M
    Subchannel modeling of single rod bowing in a bundle geometry
    Nuclear Engineering and Design. 2018; 340: 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
    DORA PSI
  • Noguere G, Tommasi J, Privas E, Schmidt K-H, Rochman D
    Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu
    European Physical Journal Plus. 2018; 133(3): 99 (14 pp.). https://doi.org/10.1140/epjp/i2018-11926-y
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Frajtag P, Pautz A
    Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
    IEEE Transactions on Nuclear Science. 2018; 65(9): 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
    DORA PSI
  • Papadionysiou M, Perret G, Zboray R, Adams R, Mosset J-B
    Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
    Nuclear Engineering and Design. 2018; 332: 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
    DORA PSI
  • Pelloni S, Rochman D
    Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
    Annals of Nuclear Energy. 2018; 115: 323-342. https://doi.org/10.1016/j.anucene.2018.01.037
    DORA PSI
  • Pelloni S, Rochman D
    Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
    Annals of Nuclear Energy. 2018; 121: 361-373. https://doi.org/10.1016/j.anucene.2018.07.043
    DORA PSI
  • Rahman S, Karanki DR, Epiney A, Wicaksono D, Zerkak O, Dang VN
    Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis
    Reliability Engineering and System Safety. 2018; 175: 62-78. https://doi.org/10.1016/j.ress.2018.03.009
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
    Consistent criticality and radiation studies of Swiss spent nuclear fuel: the CS2M approach
    Journal of Hazardous Materials. 2018; 357: 384-392. https://doi.org/10.1016/j.jhazmat.2018.05.041
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Dokhane H, Koning A
    How inelastic scattering stimulates nonlinear reactor core parameter behaviour
    Annals of Nuclear Energy. 2018; 112: 236-244. https://doi.org/10.1016/j.anucene.2017.10.018
    DORA PSI
  • Rochman D, Bauge E, Vasiliev A, Ferroukhi H, Pelloni S, Koning AJ, et al.
    Monte Carlo nuclear data adjustment via integral information
    European Physical Journal Plus. 2018; 133(12): 537. https://doi.org/10.1140/epjp/i2018-12361-x
    DORA PSI
  • Rochman DA, Bauge E, Vasiliev A, Ferroukhi H, Perret G
    Nuclear data correlation between different isotopes via integral information
    EPJ Nuclear Sciences and Technologies. 2018; 4: 7 (10 pp.). https://doi.org/10.1051/epjn/2018006
    DORA PSI
  • Rochman DA, Vasiliev A, Dokhane A, Ferroukhi H
    Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
    EPJ Nuclear Sciences and Technologies. 2018; 4: 6 (15 pp.). https://doi.org/10.1051/epjn/2018005
    DORA PSI
  • Rýdl A, Fernandez-Moguel L, Lind T
    Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
    Nuclear Technology. 2018; 205(5): 655-670. https://doi.org/10.1080/00295450.2018.1511213
    DORA PSI
  • Siefman D, Hursin M, Rochman D, Pelloni S, Pautz A
    Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
    European Physical Journal Plus. 2018; 133(10): 429 (10 pp.). https://doi.org/10.1140/epjp/i2018-12303-8
    DORA PSI
  • Simakov SP, Fischer U, Koning AJ, Konobeyev AY, Rochman DA
    Iron NRT- and arc-displacement cross sections and their covariances
    Nuclear Materials and Energy. 2018; 15: 244-248. https://doi.org/10.1016/j.nme.2018.05.006
    DORA PSI
  • Sjöstrand H, Asquith N, Helgesson P, Rochman D, van der Marck S
    Efficient use of Monte Carlo: the fast correlation coefficient
    EPJ Nuclear Sciences and Technologies. 2018; 4: 15 (5 pp.). https://doi.org/10.1051/epjn/2018019
    DORA PSI
  • Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
    On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel
    Annals of Nuclear Energy. 2018; 116: 57-68. https://doi.org/10.1016/j.anucene.2018.01.046
    DORA PSI
  • Zboray R, Trtik P
    800 fps neutron radiography of air-water two-phase flow
    MethodsX. 2018; 5: 96-102. https://doi.org/10.1016/j.mex.2018.01.008
    DORA PSI
  • Zboray R, Bolesch C, Prasser H-M
    Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
    Nuclear Engineering and Design. 2018; 336: 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
    DORA PSI

 

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2017

  • Adams R, Zboray R
    Gamma radiography and tomography with a CCD camera and Co-60 source
    Applied Radiation and Isotopes. 2017; 127: 82-86. https://doi.org/10.1016/j.apradiso.2017.05.011
    DORA PSI
  • Aures A, Bostelmann F, Hursin M, Leray O
    Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
    Annals of Nuclear Energy. 2017; 101: 262-269. https://doi.org/10.1016/j.anucene.2016.11.025
    DORA PSI
  • Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
    Analysis of the U L3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations
    Progress in Nuclear Energy. 2017; 94: 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
    DORA PSI
  • Bubelis E, Tosello A, Pfrang W, Schikorr M, Mikityuk K, Panadero A-L, et al.
    System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions
    Nuclear Engineering and Design. 2017; 320: 325-345. https://doi.org/10.1016/j.nucengdes.2017.06.015
    DORA PSI
  • Chollet M, Krsjak V, Cozzo C, Bertsch J
    Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
    EPJ Nuclear Sciences and Technologies. 2017; 3: 3 (5 pp.). https://doi.org/10.1051/epjn/2016040
    DORA PSI
  • Dehbi A, Kalilainen J, Lind T, Auvinen A
    A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
    Journal of Aerosol Science. 2017; 103: 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
    DORA PSI
  • Dokhane A, Judd J, Gajev I, Zerkak O, Ferroukhi H, Kozlowski T
    Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
    Annals of Nuclear Energy. 2017; 102: 190-199. https://doi.org/10.1016/j.anucene.2016.12.015
    DORA PSI
  • Fiorina C, Hursin M, Pautz A
    Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
    Annals of Nuclear Energy. 2017; 101: 419-428. https://doi.org/10.1016/j.anucene.2016.11.042
    DORA PSI
  • Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
    Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
    Progress in Nuclear Energy. 2017; 101: 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
    DORA PSI
  • Guo Z, Ngayam-Happy R, Krack M, Pautz A
    Atomic-scale effects of chromium-doping on defect behaviour in uranium dioxide fuel
    Journal of Nuclear Materials. 2017; 488: 160-172. https://doi.org/10.1016/j.jnucmat.2017.02.043
    DORA PSI
  • Halouane Y, Dehbi A
    CFD simulations of premixed hydrogen combustion using the Eddy Dissipation and the Turbulent Flame Closure models
    International Journal of Hydrogen Energy. 2017; 42(34): 21990-22004. https://doi.org/10.1016/j.ijhydene.2017.07.075
    DORA PSI
  • Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
    Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
    Progress in Nuclear Energy. 2017; 96: 76-96. https://doi.org/10.1016/j.pnucene.2016.11.006
    DORA PSI
  • Helgesson P, Sjöstrand H, Rochman D
    Uncertainty-driven nuclear data evaluation including thermal (n,α) applied to 59Ni
    Nuclear Data Sheets. 2017; 145: 1-24. https://doi.org/10.1016/j.nds.2017.09.001
    DORA PSI
  • Hursin M, Bogetic S, Dohkane A, Canepa S, Zerkak O, Ferroukhi H, et al.
    Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
    Annals of Nuclear Energy. 2017; 101: 559-575. https://doi.org/10.1016/j.anucene.2016.11.001
    DORA PSI
  • Karanki DR, Rahman S, Dang VN, Zerkak O
    Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
    Reliability Engineering and System Safety. 2017; 162: 91-102. https://doi.org/10.1016/j.ress.2017.01.015
    DORA PSI
  • Kelm S, Kapulla R, Allelein H-J
    Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI benchmark
    Nuclear Engineering and Design. 2017; 312: 228-238. https://doi.org/10.1016/j.nucengdes.2016.09.014
    DORA PSI
  • Kliem S, Kozmenkov Y, Hadek J, Perin Y, Fouquet F, Bernard F, et al.
    Testing the NURESIM platform on a PWR main steam line break benchmark
    Nuclear Engineering and Design. 2017; 321: 8-25. https://doi.org/10.1016/j.nucengdes.2017.05.028
    DORA PSI
  • Kéri A, Dähn R, Krack M, Churakov SV
    Combined XAFS spectroscopy and ab initio study on the characterization of iron incorporation by montmorillonite
    Environmental Science and Technology. 2017; 51(18): 10585-10594. https://doi.org/10.1021/acs.est.7b01670
    DORA PSI
  • Leray O, Ferroukhi H, Hursin M, Vasiliev A, Rochman D
    Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
    Annals of Nuclear Energy. 2017; 110: 547-559. https://doi.org/10.1016/j.anucene.2017.07.006
    DORA PSI
  • Leray O, Fiorito L, Rochman D, Ferroukhi H, Stankovskiy A, Van den Eynde G
    Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
    Progress in Nuclear Energy. 2017; 101: 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033
    DORA PSI
  • Li J, Rochman D, Vasiliev A, Ferroukhi H, Herrero J, Pautz A, et al.
    Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
    Annals of Nuclear Energy. 2017; 110: 1023-1029. https://doi.org/10.1016/j.anucene.2017.08.022
    DORA PSI
  • Li J, Rochman D, Herrero J, Vasiliev A, Ferroukhi H, Pautz A, et al.
    UO2 fuel pin bowing effects on isotopic concentrations
    Annals of Nuclear Energy. 2017; 105: 361-368. https://doi.org/10.1016/j.anucene.2017.03.038
    DORA PSI
  • Michel-Sendis F, Gauld I, Martinez JS, Alejano C, Bossant M, Boulanger D, et al.
    SFCOMPO-2.0: an OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data
    Annals of Nuclear Energy. 2017; 110: 779-788. https://doi.org/10.1016/j.anucene.2017.07.022
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Parametric study on density stratification erosion caused by a horizontal steam jet interacting with a vertical plate obstruction
    Nuclear Engineering and Design. 2017; 312: 351-360. https://doi.org/10.1016/j.nucengdes.2016.12.012
    DORA PSI
  • Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
    Annals of Nuclear Energy. 2017; 105: 121-132. https://doi.org/10.1016/j.anucene.2017.03.008
    DORA PSI
  • Pelloni S
    Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems
    Annals of Nuclear Energy. 2017; 106: 33-50. https://doi.org/10.1016/j.anucene.2017.03.040
    DORA PSI
  • Perret G, Geslot B, Gruel A, Blaise P, Di-Salvo J, De Izarra G, et al.
    Kinetic parameter measurements in the Minerve reactor
    IEEE Transactions on Nuclear Science. 2017; 64(1): 724-734. https://doi.org/10.1109/TNS.2016.2637569
    DORA PSI
  • Rochman D, Bauge E, Vasiliev A, Ferroukhi H
    Correlation ν̅p - σ - χ in the fast neutron range via integral information
    EPJ Nuclear Sciences and Technologies. 2017; 3: 14 (8 pp.). https://doi.org/10.1051/epjn/2017009
    DORA PSI
  • Rochman D, Leray O, Hursin M, Ferroukhi H, Vasiliev A, Aures A, et al.
    Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
    Nuclear Data Sheets. 2017; 139: 1-76. https://doi.org/10.1016/j.nds.2017.01.001
    DORA PSI
  • Rochman D, Goriely S, Koning AJ, Ferroukhi H
    Radiative neutron capture: Hauser Feshbach vs. statistical resonances
    Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2017; 764: 109-113. https://doi.org/10.1016/j.physletb.2016.11.018
    DORA PSI
  • Yin W, Krack M, Li X, Chen L, Liu L
    Periodic continuum solvation model integrated with first-principles calculations for solid surfaces
    Progress in Natural Science: Materials International. 2017; 27(2): 283-288. https://doi.org/10.1016/j.pnsc.2017.03.003
    DORA PSI
  • Zboray R, Adams R, Kis Z
    Fast neutron radiography and tomography at a 10 MW research reactor beamline
    Applied Radiation and Isotopes. 2017; 119: 43-50. https://doi.org/10.1016/j.apradiso.2016.10.012
    DORA PSI

 

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2016

  • Adams R, Zboray R, Prasser H-M
    A novel fast-neutron tomography system based on a plastic scintillator array and a compact D-D neutron generator
    Applied Radiation and Isotopes. 2016; 107: 1-7. https://doi.org/10.1016/j.apradiso.2015.09.002
    DORA PSI
  • Adorni M, Herranz LE, Hollands T, Ahn K-II, Bals C, D'Auria F, et al.
    OECD/NEA Sandia Fuel Project phase I: benchmark of the ignition testing
    Nuclear Engineering and Design. 2016; 307: 418-430. https://doi.org/10.1016/j.nucengdes.2016.07.016
    DORA PSI
  • Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
    On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
    Progress in Nuclear Energy. 2016; 88: 43-52. https://doi.org/10.1016/j.pnucene.2015.11.015
    DORA PSI
  • Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
    Selecting benchmarks for reactor simulations: an application to a lead fast reactor
    Annals of Nuclear Energy. 2016; 96: 158-169. https://doi.org/10.1016/j.anucene.2016.05.033
    DORA PSI
  • Andreani M, Badillo A, Kapulla R
    Synthesis of the OECD/NEA-PSI CFD benchmark exercise
    Nuclear Engineering and Design. 2016; 299: 59-80. https://doi.org/10.1016/j.nucengdes.2015.12.029
    DORA PSI
  • Beuzet E, Haurais F, Bals C, Coindreau O, Fernandez-Moguel L, Vasiliev A, et al.
    Cladding oxidation during air ingress. Part II: synthesis of modelling results
    Annals of Nuclear Energy. 2016; 93: 18-27. https://doi.org/10.1016/j.anucene.2015.12.031
    DORA PSI
  • Bozzetti C, Daellenbach KR, Hueglin C, Fermo P, Sciare J, Kasper-Giebl A, et al.
    Size-resolved identification, characterization, and quantification of primary biological organic aerosol at a European rural site
    Environmental Science and Technology. 2016; 50(7): 3425-3434. https://doi.org/10.1021/acs.est.5b05960
    DORA PSI
  • Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
    Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
    Nuclear Engineering and Design. 2016; 305: 559-568. https://doi.org/10.1016/j.nucengdes.2016.06.021
    DORA PSI
  • Brankov V, Khvostov G, Mikityuk K, Pautz A, Wiesenack W
    Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
    Nuclear Engineering and Design. 2016; 300: 97-106. https://doi.org/10.1016/j.nucengdes.2015.11.023
    DORA PSI
  • Cozzo C, Ishizaki K, Pouchon MA, Vaucher S
    Developing an in situ EXAFS experiment of microwave-induced gelation
    Journal of Sol-Gel Science and Technology. 2016; 78(3): 507-513. https://doi.org/10.1007/s10971-016-3992-5
    DORA PSI
  • Daellenbach KR, Bozzetti C, Křepelová A, Canonaco F, Wolf R, Zotter P, et al.
    Characterization and source apportionment of organic aerosol using offline aerosol mass spectrometry
    Atmospheric Measurement Techniques. 2016; 9(1): 23-39. https://doi.org/10.5194/amt-9-23-2016
    DORA PSI
  • Degueldre C, Fiorina C
    The proto-Earth geo-reactor: reassessing the hypotheses
    Solid Earth Sciences. 2016; 1(2): 49-63. https://doi.org/10.1016/j.sesci.2016.08.002
    DORA PSI
  • Dehbi A
    A unified correlation for steam condensation rates in the presence of air-helium mixtures under naturally driven flows
    Nuclear Engineering and Design. 2016; 300: 601-609. https://doi.org/10.1016/j.nucengdes.2016.02.009
    DORA PSI
  • Dehbi A, Suckow D, Lind T, Guentay S, Danner S, Mukin R
    Key findings from the artist project on aerosol retention in a dry steam generator
    Nuclear Engineering and Technology. 2016; 48(4): 870-880. https://doi.org/10.1016/j.net.2016.06.001
    DORA PSI
  • Dokhane A, Ferroukhi H, Pautz A
    Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
    Annals of Nuclear Energy. 2016; 96: 344-353. https://doi.org/10.1016/j.anucene.2016.06.016
    DORA PSI
  • Dupont J, Mignot G, Zboray R, Prasser H-M
    Infrared film thickness measurement: comparison with cold neutron imaging
    Journal of Nuclear Science and Technology. 2016; 53(5): 673-681. https://doi.org/10.1080/00223131.2015.1102779
    DORA PSI
  • Epiney A, Canepa S, Zerkak O, Ferroukhi H
    Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
    Nuclear Technology. 2016; 196(2): 223-237. https://doi.org/10.13182/NT16-47
    DORA PSI
  • Fiorina C, Kerkar N, Mikityuk K, Rubiolo P, Pautz A
    Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform
    Annals of Nuclear Energy. 2016; 96: 212-222. https://doi.org/10.1016/j.anucene.2016.05.023
    DORA PSI
  • Froidevaux P, Bochud F, Baechler S, Castella V, Augsburger M, Bailat C, et al.
    210Po poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat
    Forensic Science International. 2016; 259: 1-9. https://doi.org/10.1016/j.forsciint.2015.09.019
    DORA PSI
  • Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
    Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2016; 807: 137-149. https://doi.org/10.1016/j.nima.2015.10.024
    DORA PSI
  • Herrero JJ, Vasiliev A, Pecchia M, Ferroukhi H, Caruso S
    Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
    Annals of Nuclear Energy. 2016; 87(P2): 48-57. https://doi.org/10.1016/j.anucene.2015.08.014
    DORA PSI
  • Hursin M, Downar TJ, Yoon JI, Joo HG
    Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
    Annals of Nuclear Energy. 2016; 87: 356-365. https://doi.org/10.1016/j.anucene.2015.09.015
    DORA PSI
  • Hursin M, Scriven M, Perret G, Pautz A
    Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
    Annals of Nuclear Energy. 2016; 91: 48-58. https://doi.org/10.1016/j.anucene.2015.12.035
    DORA PSI
  • Jayaraju ST, Roelofs F, Komen EMJ, Dehbi A
    RANS modeling of fluid flow and dust deposition in nuclear pebble-beds
    Nuclear Engineering and Design. 2016; 308: 222-237. https://doi.org/10.1016/j.nucengdes.2016.08.037
    DORA PSI
  • Jäckel BS, Bevilacqua A, Ducros G, Gauntt R, Stuckert J
    Land contamination activity data interpretation from Fukushima Daiichi accident
    Nuclear Engineering and Design. 2016; 300: 28-33. https://doi.org/10.1016/j.nucengdes.2015.12.030
    DORA PSI
  • Kalilainen J, Rantanen P, Lind T, Auvinen A, Dehbi A
    Experimental investigation of a turbulent particle-laden flow inside a cubical differentially heated cavity
    Journal of Aerosol Science. 2016; 100: 73-87. https://doi.org/10.1016/j.jaerosci.2016.06.001
    DORA PSI
  • Khvostov G, Wiesenack W
    Analysis of selected Halden overpressure tests using the FALCON code
    Nuclear Engineering and Design. 2016; 310: 395-409. https://doi.org/10.1016/j.nucengdes.2016.10.033
    DORA PSI
  • Leray O, Rochman D, Grimm P, Ferroukhi H, Vasiliev A, Hursin M, et al.
    Nuclear data uncertainty propagation on spent fuel nuclide compositions
    Annals of Nuclear Energy. 2016; 94: 603-611. https://doi.org/10.1016/j.anucene.2016.03.023
    DORA PSI
  • Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
    The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle
    Progress in Nuclear Energy. 2016; 87: 144-155. https://doi.org/10.1016/j.pnucene.2014.11.016
    DORA PSI
  • Mignot G, Paranjape S, Paladino D, Jaeckel B, Rydl A
    Large scale experiments simulating hydrogen distribution in a spent fuel pool building during a hypothetical fuel uncovery accident scenario
    Nuclear Engineering and Technology. 2016; 48(4): 881-892. https://doi.org/10.1016/j.net.2016.06.005
    DORA PSI
  • Mukin RV
    Bubble reconstruction method for wire-mesh sensors measurements
    Experiments in Fluids. 2016; 57(8): 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y
    DORA PSI
  • Mukin R, Dehbi A
    Particle deposition modeling in the secondary side of a steam generator bundle model
    Nuclear Engineering and Design. 2016; 299: 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001
    DORA PSI
  • Paladino D, Andreani M, Guentay S, Mignot G, Kapulla R, Paranjape S, et al.
    Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management
    Nuclear Engineering and Design. 2016; 308: 103-114. https://doi.org/10.1016/j.nucengdes.2016.08.011
    DORA PSI
  • Pecchia M, Wicaksono D, Grimm P, Vasiliev A, Perret G, Ferroukhi H, et al.
    Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
    Annals of Nuclear Energy. 2016; 97: 153-164. https://doi.org/10.1016/j.anucene.2016.07.001
    DORA PSI
  • Pellegrini M, Dolganov K, Herranz LE, Bonneville H, Luxat D, Sonnenkalb M, et al.
    Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison
    Nuclear Technology. 2016; 196(2): 198-210. https://doi.org/10.13182/NT16-63
    DORA PSI
  • Perret G, Blaise P, Messaoudi N, Geslot B, Wagemans J, Baeten P, et al.
    Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
    Annals of Nuclear Energy. 2016; 97: 165-170. https://doi.org/10.1016/j.anucene.2016.07.015
    DORA PSI
  • Prasser H-M, Bolesch C, Cramer K, Ito D, Papadopoulos P, Saxena A, et al.
    Bubbly, slug, and annular two-phase flow in tight-lattice subchannels
    Nuclear Engineering and Technology. 2016; 48(4): 847-858. https://doi.org/10.1016/j.net.2016.06.007
    DORA PSI
  • Puragliesi R, Zhou L, Zerkak O, Pautz A
    Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments
    Nuclear Engineering and Design. 2016; 300: 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
    DORA PSI
  • Rabiti C, Alfonsi A, Epiney A
    New simulation schemes and capabilities for the PHISICS/RELAP5-3D coupled suite
    Nuclear Science and Engineering. 2016; 182(1): 104-118. https://doi.org/10.13182/NSE14-143
    DORA PSI
  • Rochman D, Leray O, Vasiliev A, Ferroukhi H, Koning AJ, Fleming M, et al.
    A Bayesian Monte Carlo method for fission yield covariance information
    Annals of Nuclear Energy. 2016; 95: 125-134. https://doi.org/10.1016/j.anucene.2016.05.005
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Zhu T, van der Marck SC, Koning AJ
    Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation
    Annals of Nuclear Energy. 2016; 92: 150-160. https://doi.org/10.1016/j.anucene.2016.01.042
    DORA PSI
  • Rochman D, Leray O, Perret G, Vasiliev A, Ferroukhi H, Koning AJ
    Re-evaluation of the thermal neutron capture cross section of 147Nd
    Annals of Nuclear Energy. 2016; 94: 612-617. https://doi.org/10.1016/j.anucene.2016.03.024
    DORA PSI
  • Rýdl A, Lind T, Birchley J
    Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data
    Nuclear Engineering and Design. 2016; 297: 175-187. https://doi.org/10.1016/j.nucengdes.2015.11.014
    DORA PSI
  • Saxena A, Zboray R, Prasser H-M
    Simulations and measurements of adiabatic annular flows in triangular, tight lattice nuclear fuel bundle model
    Nuclear Engineering and Design. 2016; 299: 163-173. https://doi.org/10.1016/j.nucengdes.2015.07.063
    DORA PSI
  • Stirling A, Rozgonyi T, Krack M, Bernasconi M
    Prebiotic NH3 formation: insights from simulations
    Inorganic Chemistry. 2016; 55(4): 1934-1939. https://doi.org/10.1021/acs.inorgchem.5b02911
    DORA PSI
  • Vasiliev A, Rochman DI, Pecchia M, Ferroukhi H
    Exploring stochastic sampling in nuclear data uncertainties assessment for reactor physics applications and validation studies
    Energies. 2016; 9(12): 1039 (18 pp.). https://doi.org/10.3390/en9121039
    DORA PSI
  • Vasiliev A, Ferroukhi H, Pecchia M, Pautz A
    Localized neutron flux assessment and verification studies using MCNPX PWR full core model
    Annals of Nuclear Energy. 2016; 92: 317-332. https://doi.org/10.1016/j.anucene.2016.01.026
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code
    Nuclear Science and Engineering. 2016; 184(3): 400-429. https://doi.org/10.13182/NSE16-37
    DORA PSI
  • Yin W-J, Wen B, Bandaru S, Krack M, Lau MW, Liu L-M
    The effect of excess electron and hole on CO2 adsorption and activation on rutile (110) surface
    Scientific Reports. 2016; 6: 23298 (9 pp.). https://doi.org/10.1038/srep23298
    DORA PSI
  • Zhang Y, Mikityuk K
    Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
    Annals of Nuclear Energy. 2016; 87: 761-771. https://doi.org/10.1016/j.anucene.2015.03.025
    DORA PSI
  • Zhu T, Vasiliev A, Ferroukhi H, Rochman D, Pautz A
    Testing the sampling-based NUSS-RF tool for the nuclear data-related global sensitivity analysis with Monte Carlo neutronics calculations
    Nuclear Science and Engineering. 2016; 184(1): 69-83. https://doi.org/10.13182/NSE14-142
    DORA PSI

 

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2015

  • Adams R, Bort L, Zboray R, Prasser H-M
    Development and characterization of a D-D fast neutron generator for imaging applications
    Applied Radiation and Isotopes. 2015; 96: 114-121. https://doi.org/10.1016/j.apradiso.2014.11.017
    DORA PSI
  • Aufiero M, Bidaud A, Hursin M, Leppänen J, Palmiotti G, Pelloni S, et al.
    A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
    Annals of Nuclear Energy. 2015; 85: 245-258. https://doi.org/10.1016/j.anucene.2015.05.008
    DORA PSI
  • Becker H, Bison G, Blau B, Chowdhuri Z, Eikenberg J, Fertl M, et al.
    Neutron production and thermal moderation at the PSI UCN source
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2015; 777: 20-27. https://doi.org/10.1016/j.nima.2014.12.091
    DORA PSI
  • Bertolus M, Freyss M, Dorado B, Martin G, Hoang K, Maillard S, et al.
    Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation
    Journal of Nuclear Materials. 2015; 462: 475-495. https://doi.org/10.1016/j.jnucmat.2015.02.026
    DORA PSI
  • Bosshard C, Deville MO, Dehbi A, Leriche E
    UDNS or LES, that is the question
    Open Journal of Fluid Dynamics. 2015; 5(4): 339-352. https://doi.org/10.4236/ojfd.2015.54034
    DORA PSI
  • Dangendorf V, Zboray R
    Potential and status in imaging with fast neutrons
    Neutron News. 2015; 26(2): 27-30. https://doi.org/10.1080/10448632.2015.1028276
    DORA PSI
  • Dehbi A
    A generalized correlation for steam condensation rates in the presence of air under turbulent free convection
    International Journal of Heat and Mass Transfer. 2015; 86: 11754 (15 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2015.02.034
    DORA PSI
  • Demeshko M, Dokhane A, Washio T, Ferroukhi H, Kawahara Y, Aguirre C
    Application of continuous and structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
    Annals of Nuclear Energy. 2015; 75: 645-657. https://doi.org/10.1016/j.anucene.2014.08.045
    DORA PSI
  • Dupont J, Mignot G, Prasser H-M
    Two-dimensional mapping of falling water film thickness with near-infrared attenuation
    Experiments in Fluids. 2015; 56(5): 90 (16 pp.). https://doi.org/10.1007/s00348-015-1955-1
    DORA PSI
  • Dupré A, Vasiliev A, Ferroukhi H, Pautz A
    Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
    Annals of Nuclear Energy. 2015; 85: 820-829. https://doi.org/10.1016/j.anucene.2015.06.040
    DORA PSI
  • Fernandez-Moguel L, Birchley J
    Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1
    Annals of Nuclear Energy. 2015; 83: 193-215. https://doi.org/10.1016/j.anucene.2015.04.021
    DORA PSI
  • Fernandez-Moguel L
    Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
    Annals of Nuclear Energy. 2015; 81: 134-142. https://doi.org/10.1016/j.anucene.2015.03.015
    DORA PSI
  • Fiorina C, Clifford I, Aufiero M, Mikityuk K
    GeN-Foam: A novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors
    Nuclear Engineering and Design. 2015; 294: 24-37. https://doi.org/10.1016/j.nucengdes.2015.05.035
    DORA PSI
  • Freixa J, Martínez-Quiroga V, Zerkak O, Reventós F
    Modelling guidelines for core exit temperature simulations with system codes
    Nuclear Engineering and Design. 2015; 286: 116-129. https://doi.org/10.1016/j.nucengdes.2015.02.003
    DORA PSI
  • Hombourger BA, Křepel J, Mikityuk K, Pautz A
    Parametric lattice study of a graphite-moderated molten salt reactor
    Journal of Nuclear Engineering and Radiation Science. 2015; 1(1): 011009 (8 pp.). https://doi.org/10.1115/1.4026401
    DORA PSI
  • Hursin M, Perret G, Pautz A
    Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
    Annals of Nuclear Energy. 2015; 77: 300-309. https://doi.org/10.1016/j.anucene.2014.11.019
    DORA PSI
  • Jayaraju ST, Sathiah P, Roelofs F, Dehbi A
    RANS modeling for particle transport and deposition in turbulent duct flows: near wall model uncertainties
    Nuclear Engineering and Design. 2015; 289: 60-72. https://doi.org/10.1016/j.nucengdes.2015.04.011
    DORA PSI
  • Jäckel BS
    Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4
    Nuclear Engineering and Design. 2015; 283: 2-7. https://doi.org/10.1016/j.nucengdes.2014.07.007
    DORA PSI
  • Karanki DR, Kim T-W, Dang VN
    A dynamic event tree informed approach to probabilistic accident sequence modeling: dynamics and variabilities in medium LOCA
    Reliability Engineering and System Safety. 2015; 142: 78-91. https://doi.org/10.1016/j.ress.2015.04.011
    DORA PSI
  • Krack M
    On the ground state electronic structure of uranium dioxide
    Physica Scripta. 2015; 90(9): 094014 (7 pp.). https://doi.org/10.1088/0031-8949/90/9/094014
    DORA PSI
  • Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
    The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle
    Progress in Nuclear Energy. 2015; 85: 498-510. https://doi.org/10.1016/j.pnucene.2015.07.020
    DORA PSI
  • Modin A, Suzuki M-T, Vegelius J, Yun Y, Shuh DK, Werme L, et al.
    5 f-shell correlation effects in dioxides of light actinides studied by O 1s x-ray absorption and emission spectroscopies and first-principles calculations
    Journal of Physics: Condensed Matter. 2015; 27(31): 315503 (8 pp.). https://doi.org/10.1088/0953-8984/27/31/315503
    DORA PSI
  • Ngayam-Happy R, Krack M, Pautz A
    Effects of stoichiometry on the defect clustering in uranium dioxide
    Journal of Physics: Condensed Matter. 2015; 27(45): 455401 (13 pp.). https://doi.org/10.1088/0953-8984/27/45/455401
    DORA PSI
  • Nikitin E, Fridman E, Mikityuk K
    On the use of the SPH method in nodal diffusion analyses of SFR cores
    Annals of Nuclear Energy. 2015; 85: 544-551. https://doi.org/10.1016/j.anucene.2015.06.007
    DORA PSI
  • Nikitin E, Fridman E, Mikityuk K
    Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
    Annals of Nuclear Energy. 2015; 75: 492-497. https://doi.org/10.1016/j.anucene.2014.08.054
    DORA PSI
  • Pecchia M, Vasiliev A, Leray O, Ferroukhi H, Pautz A
    Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
    Journal of Nuclear Science and Technology. 2015; 52(7-8): 1084-1092. https://doi.org/10.1080/00223131.2015.1032382
    DORA PSI
  • Pecchia M, Parisi C, D'Auria F, Mazzantini O
    Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
    Annals of Nuclear Energy. 2015; 85: 271-278. https://doi.org/10.1016/j.anucene.2015.05.023
    DORA PSI
  • Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    Criticality safety evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
    Annals of Nuclear Energy. 2015; 83: 226-235. https://doi.org/10.1016/j.anucene.2015.03.052
    DORA PSI
  • Perkó Z, Pelloni S, Mikityuk K, Křepel J, Szieberth M, Gaëtan G, et al.
    Core neutronics characterization of the GFR2400 gas cooled fast reactor
    Progress in Nuclear Energy. 2015; 83: 460-481. https://doi.org/10.1016/j.pnucene.2014.09.016
    DORA PSI
  • Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL
    Science and Technology of Nuclear Installations. 2015; 2015: 237646 (9 pp.). https://doi.org/10.1155/2015/237646
    DORA PSI
  • Ribeiro F, Khvostov G
    Multi-scale approach to advanced fuel modelling for enhanced safety
    Progress in Nuclear Energy. 2015; 84: 24-35. https://doi.org/10.1016/j.pnucene.2015.03.022
    DORA PSI
  • Rochman D, Koning AJ, van der Marck SC
    Improving neutronics simulations and uncertainties via a selection of nuclear data
    European Physical Journal A: Hadrons and Nuclei. 2015; 51(12): 182 (11 pp.). https://doi.org/10.1140/epja/i2015-15182-0
    DORA PSI
  • Salazar G, Zhang YL, Agrios K, Szidat S
    Development of a method for fast and automatic radiocarbon measurement of aerosol samples by online coupling of an elemental analyzer with a MICADAS AMS
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2015; 361: 163-167. https://doi.org/10.1016/j.nimb.2015.03.051
    DORA PSI
  • Siefman DJ, Girardin G, Rais A, Pautz A, Hursin M
    Full core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
    Annals of Nuclear Energy. 2015; 85: 434-443. https://doi.org/10.1016/j.anucene.2015.05.004
    DORA PSI
  • Stirling A, Rozgonyi T, Krack M, Bernasconi M
    Pyrite in contact with supercritical water: the desolation of steam
    Physical Chemistry Chemical Physics. 2015; 17(26): 17375-17379. https://doi.org/10.1039/c5cp01146a
    DORA PSI
  • Yang J, Lim J, Choi SW, Lee DY, Rassame S, Hibiki T, et al.
    Behaviors of passive safety systems under a feed water line break LOCA on a generation III + boiling water reactor
    Progress in Nuclear Energy. 2015; 83: 35-42. https://doi.org/10.1016/j.pnucene.2015.02.011
    DORA PSI
  • Yin W-J, Krack M, Wen B, Ma S-Y, Liu L-M
    CO2 capture and conversion on rutile TiO2(110) in the water environment: insight by first-principles calculations
    Journal of Physical Chemistry Letters. 2015; 6(13): 2538-2545. https://doi.org/10.1021/acs.jpclett.5b00798
    DORA PSI
  • Zanetti M, Cammi A, Fiorina C, Luzzi L
    A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
    Progress in Nuclear Energy. 2015; 83: 82-98. https://doi.org/10.1016/j.pnucene.2015.02.014
    DORA PSI
  • Zboray R, Mignot G, Kapulla R, Paladino D
    Erosion and break-up of light-gas layers by a horizontal jet in a multi-vessel, large-scale containment test system
    Nuclear Engineering and Design. 2015; 291: 10-18. https://doi.org/10.1016/j.nucengdes.2015.05.006
    DORA PSI
  • Zboray R, Dangendorf V, Mor I, Bromberger B, Tittelmeier K
    Time-resolved fast-neutron radiography of air-water two-phase flows in a rectangular channel by an improved detection system
    Review of Scientific Instruments. 2015; 86(7): 075103 (10 pp.). https://doi.org/10.1063/1.4926999
    DORA PSI
  • Zerkak O, Kozlowski T, Gajev I
    Review of multi-physics temporal coupling methods for analysis of nuclear reactors
    Annals of Nuclear Energy. 2015; 84: 225-233. https://doi.org/10.1016/j.anucene.2015.01.019
    DORA PSI
  • Zhu T, Vasiliev A, Ferroukhi H, Pautz A, Tarantola S
    NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
    Journal of Nuclear Science and Technology. 2015; 52(7-8): 1000-1007. https://doi.org/10.1080/00223131.2015.1040864
    DORA PSI
  • Zhu T, Vasiliev A, Ferroukhi H, Pautz A
    NUSS: a tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
    Annals of Nuclear Energy. 2015; 75: 713-722. https://doi.org/10.1016/j.anucene.2014.09.013
    DORA PSI

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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2010 - 2014

  • Adams R, Zboray R, Cortesi M, Prasser H-M
    Conceptual design and optimization of a plastic scintillator array for 2D tomography using a compact D-D fast neutron generator
    Applied Radiation and Isotopes. 2014; 86: 63-70. https://doi.org/10.1016/j.apradiso.2014.01.001
    DORA PSI
  • Bosshard C, Dehbi A, Deville M, Leriche E, Soldati A
    Large eddy simulation of particulate flow inside a differentially heated cavity
    Nuclear Engineering and Design. 2014; 267: 154-163. https://doi.org/10.1016/j.nucengdes.2013.12.035
    DORA PSI
  • Caruso S, Jatuff F
    Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods
    Progress in Nuclear Energy. 2014; 72: 49-54. https://doi.org/10.1016/j.pnucene.2013.09.007
    DORA PSI
  • Cortesi M, Dangendorf V, Zboray R, Prasser H-M
    A novel fast-neutron detector concept for energy-selective imaging and imaging spectroscopy
    Review of Scientific Instruments. 2014; 85(7): 073305 (8 pp.). https://doi.org/10.1063/1.4890392
    DORA PSI
  • Cozzo C, Orlov A, Borca C, Degueldre C
    X-ray absorption in plutonium uranium mixed oxide fuel: thorium characterization
    Progress in Nuclear Energy. 2014; 72: 91-95. https://doi.org/10.1016/j.pnucene.2013.09.009
    DORA PSI
  • Cripps RC, Güntay S, Jäckel B
    The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility
    Nuclear Engineering and Design. 2014; 272: 99-108. https://doi.org/10.1016/j.nucengdes.2014.02.019
    DORA PSI
  • Dokhane A, Ferroukhi H, Pautz A
    On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology
    Annals of Nuclear Energy. 2014; 67: 21-30. https://doi.org/10.1016/j.anucene.2013.11.006
    DORA PSI
  • Fernandez-Moguel L, Bals C, Beuzet E, Bratfisch C, Coindreau O, Hózer Z, et al.
    SARNET2 benchmark on air ingress experiments QUENCH-10, -16
    Annals of Nuclear Energy. 2014; 74: 12-23. https://doi.org/10.1016/j.anucene.2014.05.013
    DORA PSI
  • Ferroukhi H, Leray O, Hursin M, Vasiliev A, Perret G, Pautz A
    Study of nuclear decay data contribution to uncertainties in heat load estimations for spent fuel pools
    Nuclear Data Sheets. 2014; 118: 498-501. https://doi.org/10.1016/j.nds.2014.04.117
    DORA PSI
  • Fleurot J, Lindholm I, Kononen N, Ederli S, Jaeckel B, Kaliatka A, et al.
    Synthesis of spent fuel pool accident assessments using severe accident codes
    Annals of Nuclear Energy. 2014; 74: 58-71. https://doi.org/10.1016/j.anucene.2014.07.011
    DORA PSI
  • Geža V, Milenković RŽ, Kapulla R, Dementjevs S, Jakovičs A, Wohlmuther M
    Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target
    Nuclear Engineering and Design. 2014; 275: 96-106. https://doi.org/10.1016/j.nucengdes.2014.04.022
    DORA PSI
  • Grasso G, Petrovich C, Mattioli D, Artioli C, Sciora P, Gugiu D, et al.
    The core design of ALFRED, a demonstrator for the European lead-cooled reactors
    Nuclear Engineering and Design. 2014; 278: 287-301. https://doi.org/10.1016/j.nucengdes.2014.07.032
    DORA PSI
  • Hursin M, Collins B, Xu Y, Downar T
    The development and implementation of a one-dimensional Sn method in the 2D-1D integral transport solution
    Nuclear Science and Engineering. 2014; 176(2): 186-200. https://doi.org/10.13182/NSE12-4
    DORA PSI
  • Ihalainen M, Lind T, Arffman A, Torvela T, Jokiniemi J
    Break-Up and bounce of TiO2 agglomerates by impaction
    Aerosol Science and Technology. 2014; 48(1): 31-41. https://doi.org/10.1080/02786826.2013.852155
    DORA PSI
  • Ihalainen M, Lind T, Ruusunen J, Tiitta P, Lähde A, Torvela T, et al.
    Experimental study on bounce of submicron agglomerates upon inertial impaction
    Powder Technology. 2014; 268: 203-209. https://doi.org/10.1016/j.powtec.2014.08.029
    DORA PSI
  • Kapulla R, Mignot G, Paranjape S, Ryan L, Paladino D
    Large scale gas stratification erosion by a vertical helium-air jet
    Science and Technology of Nuclear Installations. 2014; 2014: 197267 (16 pp.). https://doi.org/10.1155/2014/197267
    DORA PSI
  • Klein-Heßling W, Sonnenkalb M, Jacquemain D, Clément B, Raimond E, Dimmelmeier H, et al.
    Conclusions on severe accident research priorities
    Annals of Nuclear Energy. 2014; 74: 4-11. https://doi.org/10.1016/j.anucene.2014.07.015
    DORA PSI
  • Křepel J, Hombourger B, Fiorina C, Mikityuk K, Rohde U, Kliem S, et al.
    Fuel cycle advantages and dynamics features of liquid fueled MSR
    Annals of Nuclear Energy. 2014; 64: 380-397. https://doi.org/10.1016/j.anucene.2013.08.007
    DORA PSI
  • Lazaro A, Schikorr M, Mikityuk K, Ammirabile L, Bandini G, Darmet G, et al.
    Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part II: optimised core and representative transients analysis
    Nuclear Engineering and Design. 2014; 277: 265-276. https://doi.org/10.1016/j.nucengdes.2014.02.029
    DORA PSI
  • Lindley BA, Fiorina C, Franceschini F, Lahoda EJ, Parks GT
    Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors
    Progress in Nuclear Energy. 2014; 77: 107-123. https://doi.org/10.1016/j.pnucene.2014.06.010
    DORA PSI
  • Lázaro A, Ammirabile L, Bandini G, Darmet G, Massara S, Dufour P, et al.
    Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part I: system description, modelling and benchmarking
    Nuclear Engineering and Design. 2014; 266: 1-16. https://doi.org/10.1016/j.nucengdes.2013.10.019
    DORA PSI
  • Lüley J, Vrban B, Čerba Š, Haščík J, Nečas V, Pelloni S
    Sensitivity and uncertainty analysis of the GFR MOX fuel subassembly
    Nuclear Data Sheets. 2014; 118: 545-547. https://doi.org/10.1016/j.nds.2014.04.130
    DORA PSI
  • Martin G, Garcia P, Sabathier C, Devynck F, Krack M, Maillard S
    A thermal modelling of displacement cascades in uranium dioxide
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2014; 327: 108-112. https://doi.org/10.1016/j.nimb.2013.09.043
    DORA PSI
  • Mukin RV
    Modeling of bubble coalescence and break-up in turbulent bubbly flow
    International Journal of Multiphase Flow. 2014; 62: 52-66. https://doi.org/10.1016/j.ijmultiphaseflow.2014.02.008
    DORA PSI
  • Ngayam-Happy R, Krack M
    Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
    Progress in Nuclear Energy. 2014; 72: 38-43. https://doi.org/10.1016/j.pnucene.2013.09.015
    DORA PSI
  • Papini D, Adamsson C, Andreani M, Prasser H-M
    Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
    Nuclear Engineering and Design. 2014; 278: 542-557. https://doi.org/10.1016/j.nucengdes.2014.08.007
    DORA PSI
  • Parisi C, Negrenti E, Pecchia M
    B&W spectral shift control reactor lattice experiments: evaluation of core I and core VIII
    Nuclear Science and Engineering. 2014; 178(4): 524-538. https://doi.org/10.13182/NSE14-40
    DORA PSI
  • Pelloni S
    Application of an iterative methodology for cross-section and variance/covariance data adjustment to the analysis of fast spectrum systems accounting for non-linearity
    Annals of Nuclear Energy. 2014; 72: 373-390. https://doi.org/10.1016/j.anucene.2014.06.002
    DORA PSI
  • Ruusunen J, Ihalainen M, Koponen T, Torvela T, Tenho M, Salonen J, et al.
    Controlled oxidation of iron nanoparticles in chemical vapour synthesis
    Journal of Nanoparticle Research. 2014; 16(2): 2270 (11 pp.). https://doi.org/10.1007/s11051-014-2270-0
    DORA PSI
  • Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, et al.
    Methods and issues for the combined use of integral experiments and covariance data: results of a NEA international collaborative study
    Nuclear Data Sheets. 2014; 118: 38-71. https://doi.org/10.1016/j.nds.2014.04.005
    DORA PSI
  • Toggweiler M, Adelmann A, Arbenz P, Yang J
    A novel adaptive time stepping variant of the Boris-Buneman integrator for the simulation of particle accelerators with space charge
    Journal of Computational Physics. 2014; 273: 255-267. https://doi.org/10.1016/j.jcp.2014.05.008
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zhu T, Pautz A
    Nuclear data library effects on fast to thermal flux shapes around PWR control rod tips
    Nuclear Data Sheets. 2014; 118: 575-578. https://doi.org/10.1016/j.nds.2014.04.139
    DORA PSI
  • Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
    Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
    Progress in Nuclear Science and Technology. 2014; 4: 99-103. https://doi.org/10.15669/pnst.4.99
    DORA PSI
  • Zboray R, Adams R, Cortesi M, Prasser H-M
    Development of a fast neutron imaging system for investigating two-phase flows in nuclear thermal-hydraulic phenomena: a status report
    Nuclear Engineering and Design. 2014; 273: 10-23. https://doi.org/10.1016/j.nucengdes.2014.01.027
    DORA PSI
  • Zboray R, Mor I, Dangendorf V, Stark M, Tittelmeier K, Cortesi M, et al.
    High-frame rate imaging of two-phase flow in a thin rectangular channel using fast neutrons
    Applied Radiation and Isotopes. 2014; 90: 122-131. https://doi.org/10.1016/j.apradiso.2014.03.023
    DORA PSI
  • Zhu T, Vasiliev A, Ferroukhi H, Pautz A
    Application of the PSI-NUSS tool for the estimation of nuclear data related keff uncertainties for the OECD/NEA WPNCS UACSA Phase I benchmark
    Nuclear Data Sheets. 2014; 118: 453-455. https://doi.org/10.1016/j.nds.2014.04.104
    DORA PSI
  • Zhu T, Rochman D, Vasiliev A, Ferroukhi H, Wieselquist W, Pautz A
    Comparison of two approaches for nuclear data uncertainty propagation in MCNPX for selected fast spectrum critical benchmarks
    Nuclear Data Sheets. 2014; 118: 388-391. https://doi.org/10.1016/j.nds.2014.04.088
    DORA PSI
  • Birchley J, Güntay S
    Significance of Phébus-FP results for plant safety in Switzerland
    Annals of Nuclear Energy. 2013; 61: 206-214. https://doi.org/10.1016/j.anucene.2013.02.032
    DORA PSI
  • Bortot S, Cammi A, Lorenzi S, Ponciroli R, Della Bona A, Juarez NB
    Stability analyses for the European LFR demonstrator
    Nuclear Engineering and Design. 2013; 265: 1238-1245. https://doi.org/10.1016/j.nucengdes.2013.09.034
    DORA PSI
  • Bosshard C, Dehbi A, Deville M, Leriche E, Puragliesi R, Soldati A
    Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method
    Computers and Fluids. 2013; 86: 210-227. https://doi.org/10.1016/j.compfluid.2013.07.007
    DORA PSI
  • Chawla R, Rätz D, Jordan KA, Perret G
    Analysis of pin removal experiments conducted in a supercritical light water reactor-like test lattice
    Nuclear Technology. 2013; 183(3): 321-330. https://doi.org/10.13182/NT13-A19421
    DORA PSI
  • Cortesi M, Zboray R, Kaestner A, Prasser H-M
    Development of a cold-neutron imaging detector based on thick gaseous electron multiplier
    Review of Scientific Instruments. 2013; 84(2): 023305 (7 pp.). https://doi.org/10.1063/1.4793225
    DORA PSI
  • Cortesi M, Zboray R, Adams R, Dangendorf V, Meshkian M, Prasser H-M
    Development of large-area THGEM detectors for investigation of thermal-hydraulic phenomena using neutron imaging
    Journal of Instrumentation. 2013; 8(10): C10009 (11 pp.). https://doi.org/10.1088/1748-0221/8/10/C10009
    DORA PSI
  • Cortesi M, Zboray R, Adams R, Dangendorf V, Breskin A, Mayer S, et al.
    First studies of electron transport along small gas gaps of novel foil radiation converters for fast-neutron detectors
    Journal of Instrumentation. 2013; 8(1): P01016 (19 pp.). https://doi.org/10.1088/1748-0221/8/01/P01016
    DORA PSI
  • Dehbi A, Badreddine H
    CFD prediction of mixing in a steam generator mock-up: comparison between full geometry and porous medium approaches
    Annals of Nuclear Energy. 2013; 58: 178-187. https://doi.org/10.1016/j.anucene.2013.03.019
    DORA PSI
  • Dehbi A
    On the adequacy of wall functions to predict condensation rates from steam-noncondensable gas mixtures
    Nuclear Engineering and Design. 2013; 265: 25-34. https://doi.org/10.1016/j.nucengdes.2013.07.014
    DORA PSI
  • Dehbi A, Janasz F, Bell B
    Prediction of steam condensation in the presence of noncondensable gases using a CFD-based approach
    Nuclear Engineering and Design. 2013; 258: 199-210. https://doi.org/10.1016/j.nucengdes.2013.02.002
    DORA PSI
  • Dokhane A, Canepa S, Ferroukhi H
    Transition to CASMO-5M and SIMULATE-3K for stability analyses of the Swiss boiling water reactors
    Nuclear Technology. 2013; 183(3): 341-353. https://doi.org/10.13182/NT13-A19423
    DORA PSI
  • Fernandez-Moguel L, Birchley J
    Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
    Annals of Nuclear Energy. 2013; 53: 202-212. https://doi.org/10.1016/j.anucene.2012.08.030
    DORA PSI
  • Fiorina C, Krepel J, Cammi A, Franceschini F, Mikityuk K, Ricotti ME
    Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure
    Annals of Nuclear Energy. 2013; 53: 492-506. https://doi.org/10.1016/j.anucene.2012.09.004
    DORA PSI
  • Fiorina C, Aufiero M, Cammi A, Franceschini F, Krepel J, Luzzi L, et al.
    Investigation of the MSFR core physics and fuel cycle characteristics
    Progress in Nuclear Energy. 2013; 68: 153-168. https://doi.org/10.1016/j.pnucene.2013.06.006
    DORA PSI
  • Freixa J, Kim T-W, Manera A
    Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation
    Nuclear Engineering and Design. 2013; 264: 153-160. https://doi.org/10.1016/j.nucengdes.2013.02.023
    DORA PSI
  • Giust FD, Grimm P, Chawla R
    Experimental validation of 3-D reconstructed pin power distributions in full-scale BWR fuel assemblies with partial-length rods
    Nuclear Science and Engineering. 2013; 175(3): 292-307. https://doi.org/10.13182/NSE12-69
    DORA PSI
  • Hursin M, Downar TJ, Montgomery R
    Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident
    Nuclear Engineering and Design. 2013; 262: 180-188. https://doi.org/10.1016/j.nucengdes.2013.04.023
    DORA PSI
  • Khvostov G, Lyon W, Zimmermann MA
    Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface
    Annals of Nuclear Energy. 2013; 62: 398-412. https://doi.org/10.1016/j.anucene.2013.07.002
    DORA PSI
  • Kröhnert H, Perret G, Murphy MF, Chawla R
    Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 698: 72-80. https://doi.org/10.1016/j.nima.2012.09.008
    DORA PSI
  • Ngayam-Happy R, Becquart CS, Domain C
    First principle-based AKMC modelling of the formation and medium-term evolution of point defect and solute-rich clusters in a neutron irradiated complex Fe-CuMnNiSiP alloy representative of reactor pressure vessel steels
    Journal of Nuclear Materials. 2013; 440(1-3): 143-152. https://doi.org/10.1016/j.jnucmat.2013.04.081
    DORA PSI
  • Rabone J, Krack M
    A procedure for bypassing metastable states in local basis set DFT+U calculations and its application to uranium dioxide surfaces
    Computational Materials Science. 2013; 71: 157-164. https://doi.org/10.1016/j.commatsci.2013.01.023
    DORA PSI
  • Rycroft CH, Dehbi A, Lind T, Güntay S
    Granular flow in pebble-bed nuclear reactors: scaling, dust generation, and stress
    Nuclear Engineering and Design. 2013; 265: 69-84. https://doi.org/10.1016/j.nucengdes.2013.07.010
    DORA PSI
  • Sun K, Krepel J, Mikityuk K, Chawla R
    A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
    Annals of Nuclear Energy. 2013; 53: 464-475. https://doi.org/10.1016/j.anucene.2012.10.004
    DORA PSI
  • Sun K, Chenu A, Krepel J, Mikityuk K, Chawla R
    Coupled 3-D neutronics/thermal-hydraulics optimization study for improving the response of a 3600 MW(thermal) SFR core to an unprotected loss-of-flow accident
    Nuclear Technology. 2013; 183(3): 484-503. https://doi.org/10.13182/NT13-A19436
    DORA PSI
  • Tenchine D, Pialla D, Fanning TH, Thomas JW, Chellapandi P, Shvetsov Y, et al.
    International benchmark on the natural convection test in Phenix reactor
    Nuclear Engineering and Design. 2013; 258: 189-198. https://doi.org/10.1016/j.nucengdes.2013.02.010
    DORA PSI
  • Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H
    PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark phase I
    Science and Technology of Nuclear Installations. 2013; 2013: 549793 (15 pp.). https://doi.org/10.1155/2013/549793
    DORA PSI
  • Yang JJ, Adelmann A, Barletta W, Calabretta L, Calanna A, Campo D, et al.
    Beam dynamics simulation for the high intensity DAEδALUS cyclotrons
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 704: 84-91. https://doi.org/10.1016/j.nima.2012.12.050
    DORA PSI
  • Zboray R, Prasser H-M
    Measuring liquid film thickness in annular two-phase flows by cold neutron imaging
    Experiments in Fluids. 2013; 54(9): 1596 (15 pp.). https://doi.org/10.1007/s00348-013-1596-1
    DORA PSI
  • Zboray R, Prasser H-M
    Neutron imaging of annular flows in a tight lattice fuel bundle model
    Nuclear Engineering and Design. 2013; 262: 589-599. https://doi.org/10.1016/j.nucengdes.2013.06.005
    DORA PSI
  • Zboray R, Prasser H-M
    Optimizing the performance of cold-neutron tomography for investigating annular flows and functional spacers in fuel rod bundles
    Nuclear Engineering and Design. 2013; 260: 188-203. https://doi.org/10.1016/j.nucengdes.2013.03.026
    DORA PSI
  • Ammar Y, Dehbi A, Reeks MW
    Break-up of aerosol agglomerates in highly turbulent gas flow
    Flow, Turbulence and Combustion. 2012; 89(3): 465-489. https://doi.org/10.1007/s10494-012-9398-8
    DORA PSI
  • Andreani M, Bittermann D, Marsault P, Antoni O, Keresztúri A, Schlagenhaufer M, et al.
    Evaluation of a preliminary safety concept for the HPLWR
    Progress in Nuclear Energy. 2012; 55: 68-77. https://doi.org/10.1016/j.pnucene.2011.11.004
    DORA PSI
  • Aounallah Y
    Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
    Kerntechnik. 2012; 77(5): 316-323. https://doi.org/10.3139/124.110214
    DORA PSI
  • Arazi L, Natal da Luz H, Freytag D, Pitt M, Azevedo CDR, Rubin A, et al.
    THGEM-based detectors for sampling elements in DHCAL: laboratory and beam evaluation
    Journal of Instrumentation. 2012; 7(5): C05011 (15 pp.). https://doi.org/10.1088/1748-0221/7/05/C05011
    DORA PSI
  • Birchley J, Fernandez-Moguel L
    Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development
    Annals of Nuclear Energy. 2012; 40(1): 163-170. https://doi.org/10.1016/j.anucene.2011.10.019
    DORA PSI
  • Bottomley D, Stuckert J, Hofmann P, Tocheny L, Hugon M, Journeau C, et al.
    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
    Nuclear Engineering and Design. 2012; 252: 226-241. https://doi.org/10.1016/j.nucengdes.2012.07.006
    DORA PSI
  • Breskin A, Israelashvili I, Cortesi M, Arazi L, Shchemelinin S, Chechik R, et al.
    A novel liquid-xenon detector concept for combined fast-neutrons and gamma imaging and spectroscopy
    Journal of Instrumentation. 2012; 7(6): C06008 (14 pp.). https://doi.org/10.1088/1748-0221/7/06/C06008
    DORA PSI
  • Chenu A, Adams R, Mikityuk K, Chawla R
    Analysis of selected Phenix EOL tests with the FAST code system - part I: control-rod-shift experiments
    Annals of Nuclear Energy. 2012; 49: 182-190. https://doi.org/10.1016/j.anucene.2012.05.036
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    Analysis of selected Phenix EOL tests with the FAST code system - part II: unprotected phase of the Natural Convection Test
    Annals of Nuclear Energy. 2012; 49: 191-199. https://doi.org/10.1016/j.anucene.2012.05.035
    DORA PSI
  • Cortesi M, Zboray R, Adams R, Dangendorf V, Prasser H-M
    Concept of a novel fast neutron imaging detector based on THGEM for fan-beam tomography applications
    Journal of Instrumentation. 2012; 7(2): C02056 (11 pp.). https://doi.org/10.1088/1748-0221/7/02/C02056
    DORA PSI
  • Devynck F, Iannuzzi M, Krack M
    Frenkel pair recombinations in UO2: importance of explicit description of polarizability in core-shell molecular dynamics simulations
    Physical Review B. 2012; 85(18): 184103 (12 pp.). https://doi.org/10.1103/PhysRevB.85.184103
    DORA PSI
  • Dietler R, Hursin M, Perret G, Jordan K, Chawla R
    A novel design approach for a neutron measurement station for burnt fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2012; 693: 59-66. https://doi.org/10.1016/j.nima.2012.07.009
    DORA PSI
  • Epiney A, Alpy N, Mikityuk K, Chawla R
    A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions
    Nuclear Engineering and Design. 2012; 242: 267-284. https://doi.org/10.1016/j.nucengdes.2011.10.011
    DORA PSI
  • Fernandez-Moguel L, Birchley J
    Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM
    Annals of Nuclear Energy. 2012; 40(1): 141-152. https://doi.org/10.1016/j.anucene.2011.10.018
    DORA PSI
  • Freixa J, Manera A
    Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility
    Science and Technology of Nuclear Installations. 2012; 2012: 158617 (17 pp.). https://doi.org/10.1155/2012/158617
    DORA PSI
  • Freixa J, Kim T-W, Manera A
    Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation
    Nuclear Engineering and Design. 2012; 249: 97-103. https://doi.org/10.1016/j.nucengdes.2011.08.061
    DORA PSI
  • Girault N, Bosland L, Dickinson S, Funke F, Güntay S, Herranz LE, et al.
    LWR severe accident simulation: iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
    Nuclear Engineering and Design. 2012; 243: 371-392. https://doi.org/10.1016/j.nucengdes.2011.11.011
    DORA PSI
  • Ihalainen M, Lind T, Torvela T, Lehtinen KEJ, Jokiniemi J
    A method to study agglomerate breakup and bounce during impaction
    Aerosol Science and Technology. 2012; 46(9): 990-1001. https://doi.org/10.1080/02786826.2012.685663
    DORA PSI
  • Kapulla R, Mignot G, Paladino D
    Large-scale containment cooler performance experiments under accident conditions
    Science and Technology of Nuclear Installations. 2012; 2012: 943197 (20 pp.). https://doi.org/10.1155/2012/943197
    DORA PSI
  • Kim T, Petrov V, Manera A, Lo S
    Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes
    Science and Technology of Nuclear Installations. 2012; 2012: 746467 (20 pp.). https://doi.org/10.1155/2012/746467
    DORA PSI
  • Kim TW, Dang VN, Zimmermann MA, Manera A
    Quantitative evaluation of change in core damage frequency by postulated power uprate: medium-break loss-of-coolant-accidents
    Annals of Nuclear Energy. 2012; 47: 69-80. https://doi.org/10.1016/j.anucene.2012.04.021
    DORA PSI
  • Kozmenkov Y, Rohde U, Manera A
    Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility
    Nuclear Engineering and Design. 2012; 243: 168-175. https://doi.org/10.1016/j.nucengdes.2011.10.053
    DORA PSI
  • Krepel J, Pelloni S, Mikityuk K
    Comparison of open and closed U-Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure
    Nuclear Engineering and Design. 2012; 250: 392-402. https://doi.org/10.1016/j.nucengdes.2012.06.004
    DORA PSI
  • Marinoni A, Girardin G, Mikityuk K
    Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX
    Annals of Nuclear Energy. 2012; 44: 26-33. https://doi.org/10.1016/j.anucene.2012.01.011
    DORA PSI
  • Paladino D, Dreier J
    PANDA: a multipurpose integral test facility for LWR safety investigations
    Science and Technology of Nuclear Installations. 2012; 2012: 239319 (9 pp.). https://doi.org/10.1155/2012/239319
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  • Paladino D, Dreier J
    Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas
    Nuclear Engineering and Design. 2012; 247: 212-220. https://doi.org/10.1016/j.nucengdes.2012.03.006
    DORA PSI
  • Perret G, Jordan KA
    On the combination of delayed neutron and delayed gamma measurement techniques for nuclear fuel and its application to nuclear data uncertainty reduction
    IEEE Transactions on Nuclear Science. 2012; 59(6): 3166-3172. https://doi.org/10.1109/TNS.2012.2215339
    DORA PSI
  • Rätz D, Jordan KA, Bayard A-SP, Perret G, Chawla R
    Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice
    Nuclear Engineering and Design. 2012; 247: 236-247. https://doi.org/10.1016/j.nucengdes.2012.02.011
    DORA PSI
  • Sharabi M, Freixa J
    Analysis of the ISP-50 Direct Vessel Injection SBLOCA in the ATLAS facility with the RELAP5/MOD3.3 code
    Nuclear Engineering and Technology. 2012; 44(7): 709-718. https://doi.org/10.5516/NET.02.2012.712
    DORA PSI
  • Yun Y, Legut D, Oppeneer PM
    Phonon spectrum, thermal expansion and heat capacity of UO2 from first-principles
    Journal of Nuclear Materials. 2012; 426(1-3): 109-114. https://doi.org/10.1016/j.jnucmat.2012.03.017
    DORA PSI
  • Adamsson C, Le Corre J-M
    Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies
    Nuclear Engineering and Design. 2011; 241(8): 2843-2858. https://doi.org/10.1016/j.nucengdes.2011.01.033
    DORA PSI
  • Barten W, Jasiulevicius A, Zerkak O, Macian-Juan R
    Analysis of the umsichtwater hammer benchmark experiment 329 using trace and RELAP5
    Multiphase Science and Technology. 2011; 23(1): 1-27. https://doi.org/10.1615/MultScienTechn.v23.i1.10
    DORA PSI
  • Bertolotto D, Manera A, Macián-Juan R, Chawla R
    Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm
    Nuclear Engineering and Design. 2011; 241(1): 245-256. https://doi.org/10.1016/j.nucengdes.2010.10.021
    DORA PSI
  • Caravati S, Colleoni D, Mazzarello R, Kühne TD, Krack M, Bernasconi M, et al.
    First-principles study of nitrogen doping in cubic and amorphous Ge2Sb2Te5
    Journal of Physics: Condensed Matter. 2011; 23(26): 265801 (13 pp.). https://doi.org/10.1088/0953-8984/23/26/265801
    DORA PSI
  • Chauliac C, Aragonés J-M, Bestion D, Cacuci DG, Crouzet N, Weiss F-P, et al.
    NURESIM - A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis
    Nuclear Engineering and Design. 2011; 241(9): 3416-3426. https://doi.org/10.1016/j.nucengdes.2010.09.040
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow
    Nuclear Engineering and Design. 2011; 241(9): 3898-3909. https://doi.org/10.1016/j.nucengdes.2011.07.009
    DORA PSI
  • Chylarecka D, Kim TK, Tarafder K, Müller K, Gödel K, Czekaj I, et al.
    Indirect magnetic coupling of manganese porphyrin to a ferromagnetic cobalt substrate
    Journal of Physical Chemistry C. 2011; 115(4): 1295-1301. https://doi.org/10.1021/jp106822s
    DORA PSI
  • Freixa J, Manera A
    Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test
    Nuclear Engineering and Design. 2011; 241(3): 888-896. https://doi.org/10.1016/j.nucengdes.2010.12.016
    DORA PSI
  • Giust FD, Grimm P, Chawla R
    Experimental comparisons of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies
    Journal of Engineering for Gas Turbines and Power. 2011; 133(5): 52909 (13 pp.). https://doi.org/10.1115/1.4002823
    DORA PSI
  • Herranz LE, Vallejo I, Khvostov G, Sercombe J, Zhou G
    Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project
    Nuclear Engineering and Design. 2011; 241(3): 815 (11 pp.)-825. https://doi.org/10.1016/j.nucengdes.2011.01.007
    DORA PSI
  • Jordan KA, Perret G
    A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2011; 634(1): 91-100. https://doi.org/10.1016/j.nima.2011.01.064
    DORA PSI
  • Khvostov G, Mikityuk K, Zimmermann MA
    A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code
    Nuclear Engineering and Design. 2011; 241(8): 2983-3007. https://doi.org/10.1016/j.nucengdes.2011.06.020
    DORA PSI
  • Khvostov G, Wiesenack W, Zimmermann MA, Ledergerber G
    Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
    Nuclear Engineering and Design. 2011; 241(5): 1500-1507. https://doi.org/10.1016/j.nucengdes.2011.03.003
    DORA PSI
  • Kolbe E, Vasiliev A, Ferroukhi H
    Assessment of the JEFF-3.1.1 neutron data library for CSE of LWR fuel storage pools
    Journal of the Korean Physical Society. 2011; 59(23): 1174-1178. https://doi.org/10.3938/jkps.59.1174
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  • Mikityuk K, Shestopalov A
    FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests
    Nuclear engineering and design. 2011; 241(7): 2455-2461. https://doi.org/10.1016/j.nucengdes.2011.04.033
    DORA PSI
  • Modin A, Yun Y, Suzuki M-T, Vegelius J, Werme L, Nordgren J, et al.
    Indication of single-crystal PuO2 oxidation from O 1s x-ray absorption spectra
    Physical Review B. 2011; 83(7): 075113 (7 pp.). https://doi.org/10.1103/PhysRevB.83.075113
    DORA PSI
  • Nikitin K, Manera A
    Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
    Nuclear Engineering and Design. 2011; 241(6): 2240-2247. https://doi.org/10.1016/j.nucengdes.2011.03.021
    DORA PSI
  • Pelloni S, Mikityuk K
    A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors
    Annals of Nuclear Energy. 2011; 38(1): 1-13. https://doi.org/10.1016/j.anucene.2010.08.009
    DORA PSI
  • Perez M, Reventos F, Batet L, Guba A, Tóth I, Mieusset T, et al.
    Uncertainty and sensitivity analysis of a LBLOCA in a PWR nuclear power plant: results of the phase V of the BEMUSE programme
    Nuclear Engineering and Design. 2011; 241(10): 4206-4222. https://doi.org/10.1016/j.nucengdes.2011.08.019
    DORA PSI
  • Petrov V, Manera A
    Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPRTM: CFD investigations and comparison with experimental results
    Nuclear Engineering and Design. 2011; 241(5): 1478-1485. https://doi.org/10.1016/j.nucengdes.2011.02.027
    DORA PSI
  • Pittarello R, Vasiliev A, Ferroukhi H, Chawla R
    Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark
    Annals of Nuclear Energy. 2011; 38(9): 1842-1851. https://doi.org/10.1016/j.anucene.2011.05.017
    DORA PSI
  • Rätz D, Jordan KA, Murphy MF, Perret G, Chawla R
    Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice
    Annals of Nuclear Energy. 2011; 38(4): 794-801. https://doi.org/10.1016/j.anucene.2010.11.021
    DORA PSI
  • Rätz D, Jordan KA, Perret G, Chawla R
    Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice
    Annals of Nuclear Energy. 2011; 38(11): 2319-2332. https://doi.org/10.1016/j.anucene.2011.07.007
    DORA PSI
  • Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
    Gas cooled fast reactor research in Europe
    Nuclear Engineering and Design. 2011; 241(9): 3481-3489. https://doi.org/10.1016/j.nucengdes.2011.08.005
    DORA PSI
  • Sun K, Krepel J, Mikityuk K, Pelloni S, Chawla R
    Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
    Annals of Nuclear Energy. 2011; 38(7): 1645-1657. https://doi.org/10.1016/j.anucene.2011.02.018
    DORA PSI
  • Vasiliev A, Kolbe E, Ferroukhi H, Pittarello R
    Comparison of neutron data libraries for the analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX code
    Journal of the Korean Physical Society. 2011; 59(23): 2047-2050. https://doi.org/10.3938/jkps.59.2047
    DORA PSI
  • Vinai P, Macian-Juan R, Chawla R
    Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
    Annals of Nuclear Energy. 2011; 38(2-3): 358-370. https://doi.org/10.1016/j.anucene.2010.10.007
    DORA PSI
  • Yun Y, Oppeneer PM
    First-principles design of next-generation nuclear fuels
    MRS Bulletin. 2011; 36(3): 178-184. https://doi.org/10.1557/mrs.2011.34
    DORA PSI
  • Yun Y, Rusz J, Suzuki M-T, Oppeneer PM
    First-principles investigation of higher oxides of uranium and neptunium: U3O8 and Np2O5
    Physical Review B. 2011; 83(7): 075109 (10 pp.). https://doi.org/10.1103/PhysRevB.83.075109
    DORA PSI
  • Zerkak O, Ferroukhi H
    Vessel coolant mixing effects on a PWR Main Steam Line Break transient
    Annals of Nuclear Energy. 2011; 38(1): 60-71. https://doi.org/10.1016/j.anucene.2010.08.016
    DORA PSI
  • Aounallah Y
    Development of a wide-range pre-CHF convective boiling correlation
    Journal of Nuclear Science and Technology. 2010; 47(4): 357-366. https://doi.org/10.3327/jnst.47.357
    DORA PSI
  • Epiney A, Mikityuk K, Chawla R
    Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions
    Nuclear Engineering and Design. 2010; 240(10): 3115-3125. https://doi.org/10.1016/j.nucengdes.2010.05.030
    DORA PSI
  • Epiney A, Mikityuk K, Chawla R
    TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods
    Annals of Nuclear Energy. 2010; 37(6): 875-887. https://doi.org/10.1016/j.anucene.2010.01.020
    DORA PSI
  • Freixa J, Manera A
    Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE
    Nuclear Engineering and Design. 2010; 240(7): 1779-1788. https://doi.org/10.1016/j.nucengdes.2010.02.007
    DORA PSI
  • Kolbe E, Vasiliev A, Ferroukhi H
    The effect of modern thermal neutron scattering sublibraries on criticality safety evaluations of wet storage pools
    Annals of Nuclear Energy. 2010; 37(3): 371-379. https://doi.org/10.1016/j.anucene.2009.12.003
    DORA PSI
  • Kosa M, Tan J-C, Merrill CA, Krack M, Cheetham AK, Parrinello M
    Probing the mechanical properties of hybrid inorganic-organic frameworks: a computational and experimental study
    ChemPhysChem. 2010; 11(11): 2332-2336. https://doi.org/10.1002/cphc.201000362
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  • Krepel J, Pelloni S, Mikityuk K, Coddington P
    GFR equilibrium cycle analysis with the EQL3D procedure
    Nuclear Engineering and Design. 2010; 240(4): 905-917. https://doi.org/10.1016/j.nucengdes.2009.12.007
    DORA PSI
  • Kröhnert H, Perret G, Murphy MF, Chawla R
    Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2010; 624(1): 101-108. https://doi.org/10.1016/j.nima.2010.09.033
    DORA PSI
  • Mikityuk K
    Analytical model of the oxide layer build-up in complex lead-cooled systems
    Nuclear Engineering and Design. 2010; 240(10): 3632-3637. https://doi.org/10.1016/j.nucengdes.2010.07.005
    DORA PSI
  • Mikityuk K, Krepel J, Pelloni S, Chenu A, Petkevich P, Chawla R
    FAST code system: review of recent developments and near-future plans
    Journal of Engineering for Gas Turbines and Power. 2010; 132(10): 102915 (7 pp.). https://doi.org/10.1115/1.4000336
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  • Pérez M, Reventós F, Batet L, Pericas R, Toth I, Bazin P, et al.
    Main Results of phase IV BEMUSE project: simulation of LBLOCA in an NPP
    Science and Technology of Nuclear Installations. 2010; 2010: 219294 (9 pp.). https://doi.org/10.1155/2010/219294
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  • Rohde M, Marcel CP, Manera A, Van der Hagen THJJ, Shiralkar B
    Investigating the ESBWR stability with experimental and numerical tools: a comparative study
    Nuclear Engineering and Design. 2010; 240(2): 375-384. https://doi.org/10.1016/j.nucengdes.2008.01.016
    DORA PSI
  • Vasiliev A, Ferroukhi H, Kolbe E
    Performance of a Monte-Carlo solution for the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
    Annals of Nuclear Energy. 2010; 37(10): 1404-1410. https://doi.org/10.1016/j.anucene.2010.05.019
    DORA PSI
  • Walker C, Manera A, Niceno B, Simiano M, Prasser HM
    Steady-state RANS-simulations of the mixing in a T-junction
    Nuclear Engineering and Design. 2010; 240(9): 2107-2115. https://doi.org/10.1016/j.nucengdes.2010.05.056
    DORA PSI

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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2005 - 2009

  • Bertolotto D, Manera A, Frey S, Prasser H-M, Chawla R
    Single-phase mixing studies by means of a directly coupled CFD/system-code tool
    Annals of Nuclear Energy. 2009; 36(3): 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
    DORA PSI
  • Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
    First-principles study of crystalline and amorphous Ge2Sb2Te5 and the effects of stoichiometric defects
    Journal of Physics: Condensed Matter. 2009; 21(25): 255501 (14 pp.). https://doi.org/10.1088/0953-8984/21/25/255501
    DORA PSI
  • Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
    Unravelling the mechanism of pressure induced amorphization of phase change materials
    Physical Review Letters. 2009; 102(20): 205502 (4 pp.). https://doi.org/10.1103/PhysRevLett.102.205502
    DORA PSI
  • Caruso S, Murphy MF, Jatuff F, Chawla R
    Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography
    Nuclear Engineering and Design. 2009; 239(7): 1220-1228. https://doi.org/10.1016/j.nucengdes.2009.02.019
    DORA PSI
  • Chawla R
    Editorial
    Annals of Nuclear Energy. 2009; 36(3): 255-257. https://doi.org/10.1016/j.anucene.2008.11.008
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions
    Nuclear Engineering and Design. 2009; 239(11): 2417-2429. https://doi.org/10.1016/j.nucengdes.2009.07.015
    DORA PSI
  • Cucinotta CS, Miceli G, Raiteri P, Krack M, Kühne TD, Bernasconi M, et al.
    Superionic conduction in substoichiometric LiAl alloy: an Ab Initio study
    Physical Review Letters. 2009; 103(12): 125901 (4 pp.). https://doi.org/10.1103/PhysRevLett.103.125901
    DORA PSI
  • Ferroukhi H, Zerkak O, Chawla R
    Cross-section modelling effects on pressurised water reactor main steam line break analyses
    Annals of Nuclear Energy. 2009; 36(8): 1184-1200. https://doi.org/10.1016/j.anucene.2009.04.006
    DORA PSI
  • Ferroukhi H, Hollard JM, Zimmermann MA, Chawla R
    Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme
    Annals of Nuclear Energy. 2009; 36(3): 286-291. https://doi.org/10.1016/j.anucene.2008.12.010
    DORA PSI
  • Ferroukhi H, Zimmermann MA
    Study of the PWR REA pulse width for realistic UO2 and MOX core designs using 3D kinetics methods
    Annals of Nuclear Energy. 2009; 36(8): 1170-1183. https://doi.org/10.1016/j.anucene.2009.04.007
    DORA PSI
  • Jatuff F, Perret G, Murphy MF, Giust F, Chawla R
    Void reactivity coefficient benchmark results for a 10 × 10 BWR assembly in the full 0-100% void fraction range
    Annals of Nuclear Energy. 2009; 36(6): 853-858. https://doi.org/10.1016/j.anucene.2009.02.013
    DORA PSI
  • Kato Y, Tsuzuki N, Nikitin K, Ishizuka T
    Advanced microchannel heat exchanger with S-shaped fins
    Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.1080/18811248.2007.9711547
    DORA PSI
  • Krepel J, Pelloni S, Mikityuk K, Coddington P
    EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
    Annals of Nuclear Energy. 2009; 36(5): 550-561. https://doi.org/10.1016/j.anucene.2009.01.008
    DORA PSI
  • Kühne TD, Krack M, Parrinello M
    Static and dynamical properties of liquid water from first principles by a novel Car-Parrinello-like approach
    Journal of Chemical Theory and Computation. 2009; 5(2): 235-241. https://doi.org/10.1021/ct800417q
    DORA PSI
  • Liu L-M, Krack M, Michaelides A
    Interfacial water: a first principles molecular dynamics study of a nanoscale water film on salt
    Journal of Chemical Physics. 2009; 130(23): 234702 (12 pp.). https://doi.org/10.1063/1.3152845
    DORA PSI
  • Manera A, Ozar B, Paranjape S, Ishii M, Prasser H-M
    Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
    Nuclear Engineering and Design. 2009; 239(9): 1718-1724. https://doi.org/10.1016/j.nucengdes.2008.06.015
    DORA PSI
  • Mikityuk K
    Heat transfer to liquid metal: review of data and correlations for tube bundles
    Nuclear Engineering and Design. 2009; 239(4): 680-687. https://doi.org/10.1016/j.nucengdes.2008.12.014
    DORA PSI
  • Perret G, Murphy MF, Jatuff F, Sublet JC, Bouland O, Chawla R
    Impact of new gadolinium cross sections on reaction rate distributions in 10×10 BWR assemblies
    Nuclear Science and Engineering. 2009; 163(1): 17-25. https://doi.org/10.13182/NSE08-55
    DORA PSI
  • Petkevich P, Mikityuk K, Coddington P, Chawla R
    Development and benchmarking of a mechanical model for GFR plate-type fuel
    Annals of Nuclear Energy. 2009; 36(8): 1262-1269. https://doi.org/10.1016/j.anucene.2009.01.015
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
    Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.3327/jnst.46.933
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
    Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.1080/18811248.2009.9711602
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Perret G, Seiler R, Chawla R
    Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model
    Annals of Nuclear Energy. 2009; 36(10): 1536-1543. https://doi.org/10.1016/j.anucene.2009.07.012
    DORA PSI
  • Romano A, Shuffler CA, Garkisch HD, Olander DR, Todreas NE
    Fuel performance analysis for PWR cores
    Nuclear Engineering and Design. 2009; 239(8): 1481-1488. https://doi.org/10.1016/j.nucengdes.2008.11.022
    DORA PSI
  • Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
    Gas cooled fast reactor research and development in the European Union
    Science and Technology of Nuclear Installations. 2009; 2009: 238624 (7 pp.). https://doi.org/10.1155/2009/238624
    DORA PSI
  • Tsuzuki N, Kato Y, Nikitin K, Ishizuka T
    Advanced microchannel heat exchanger with S-shaped fins
    Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.3327/jnst.46.403
    DORA PSI
  • Aounallah Y
    A separate-effect-based new appraisal of convective boiling and its suppression
    Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.3327/jnst.45.149
    DORA PSI
  • Barten W, Jasiulevicius A, Manera A, Macian-Juan R, Zerkak O
    Analysis of the capability of system codes to model cavitation water hammers: simulation of UMSICHT water hammer experiments with TRACE and RELAP5
    Nuclear Engineering and Design. 2008; 238(4): 1129-1145. https://doi.org/10.1016/j.nucengdes.2007.10.004
    DORA PSI
  • Barten W, Manera A, Macian-Juan R
    One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
    Nuclear Engineering and Design. 2008; 238(10): 2568-2582. https://doi.org/10.1016/j.nucengdes.2008.05.004
    DORA PSI
  • Blair P, Khvostov G, Romano A, Hellwig C, Chawla R
    Interpretation of high-burnup fuel annealing tests
    Journal of Nuclear Science and Technology. 2008; 45(7): 639-646. https://doi.org/10.1080/18811248.2008.9711463
    DORA PSI
  • Bubelis E, Castelliti D, Coddington P, Dor I, Fouillet C, de Geus E, et al.
    A GFR benchmark: comparison of transient analysis codes based on the ETDR concept
    Progress in Nuclear Energy. 2008; 50(1): 37-51. https://doi.org/10.1016/j.pnucene.2007.11.090
    DORA PSI
  • Bubelis E, Coddington P, Mikityuk K
    Verification of the TRACE code against the MEGAPIE transient data
    Annals of Nuclear Energy. 2008; 35(7): 1284-1295. https://doi.org/10.1016/j.anucene.2007.12.006
    DORA PSI
  • Caruso S, Günther-Leopold I, Murphy MF, Jatuff F, Chawla R
    Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2008; 589(3): 425-435. https://doi.org/10.1016/j.nima.2008.03.005
    DORA PSI
  • Caruso S, Murphy MF, Jatuff F, Chawla R
    Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography
    Journal of Nuclear Science and Technology. 2008; 45(8): 828-835. https://doi.org/10.3327/jnst.45.828
    DORA PSI
  • Chawla R, Jatuff F, Tani F
    Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice
    Annals of Nuclear Energy. 2008; 35(3): 495-502. https://doi.org/10.1016/j.anucene.2007.06.027
    DORA PSI
  • Cometto M, Wydler P, Chawla R
    Management of actinide waste inventories in nuclear phase-out scenarios
    Annals of Nuclear Energy. 2008; 35(8): 1447-1460. https://doi.org/10.1016/j.anucene.2008.01.016
    DORA PSI
  • Girardin G, Rimpault G, Morin F, Bosq JC, Coddington P, Mikityuk K, et al.
    Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
    Annals of Nuclear Energy. 2008; 35(12): 2206-2218. https://doi.org/10.1016/j.anucene.2008.09.008
    DORA PSI
  • Kolbe E, Vasiliev A, Ferroukhi H, Zimmermann MA
    Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems
    Annals of Nuclear Energy. 2008; 35(10): 1831-1841. https://doi.org/10.1016/j.anucene.2008.04.009
    DORA PSI
  • Kosa M, Krack M, Cheetham AK, Parrinello M
    Modeling the hydrogen storage materials with exposed M2+ coordination sites
    Journal of Physical Chemistry C. 2008; 112(42): 16171-16173. https://doi.org/10.1021/jp806394g
    DORA PSI
  • Krepel J, Rohde U, Grundmann U, Weiss F-P
    Dynamics of molten salt reactors
    Nuclear Technology. 2008; 164(1): 34-44. https://doi.org/10.13182/NT08-A4006
    DORA PSI
  • Liu L, Krack M, Michaelides A
    Density oscillations in a nanoscale water film on salt: insight from ab initio molecular dynamics
    Journal of the American Chemical Society. 2008; 130(27): 8572-8573. https://doi.org/10.1021/ja8014296
    DORA PSI
  • Mikityuk K, Coddington P, Gröschel F
    Analysis of radioactivity releases in the MEGAPIE reference accident
    Nuclear Engineering and Design. 2008; 238(7): 1838-1844. https://doi.org/10.1016/j.nucengdes.2007.12.004
    DORA PSI
  • Murphy MF, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
    Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions
    Annals of Nuclear Energy. 2008; 35(11): 2042-2050. https://doi.org/10.1016/j.anucene.2008.06.001
    DORA PSI
  • Perret G, Plaschy M, Murphy MF, Jatuff F, Chawla R
    Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly
    Annals of Nuclear Energy. 2008; 35(3): 478-484. https://doi.org/10.1016/j.anucene.2007.06.025
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
    On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test
    Annals of Nuclear Energy. 2008; 35(4): 565-569. https://doi.org/10.1016/j.anucene.2007.08.018
    DORA PSI
  • Vasiliev A, Kolbe E, Ferroukhi H, Zimmermann MA, Chawla R
    On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
    Annals of Nuclear Energy. 2008; 35(12): 2432-2435. https://doi.org/10.1016/j.anucene.2008.07.009
    DORA PSI
  • Vasiliev A, Kolbe E, Zimmermann MA
    Towards the development of upper subcriticality limits on the basis of benchmark criticality calculations
    Annals of Nuclear Energy. 2008; 35(9): 1764-1773. https://doi.org/10.1016/j.anucene.2008.01.017
    DORA PSI
  • Bergmann UC, Grimm P, Jatuff F, Murphy MF, Chawla R
    Investigations of 238U captures to total fissions in a Westinghouse SVEA-96+ assembly
    Nuclear Science and Engineering. 2007; 156(1): 86-95. https://doi.org/10.13182/NSE07-A2687
    DORA PSI
  • Caruso S, Murphy M, Jatuff F, Chawla R
    Validation of of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel
    Annals of Nuclear Energy. 2007; 34(1-2): 28-35. https://doi.org/10.1016/j.anucene.2006.11.009
    DORA PSI
  • Dokhane A, Hennig D, Rizwan-uddin, Chawla R
    BWR stability and bifurcation analysis using reduced order models and system codes: identification of a subcritical Hopf bifurcation using RAMONA
    Annals of Nuclear Energy. 2007; 34(10): 792-802. https://doi.org/10.1016/j.anucene.2007.04.003
    DORA PSI
  • Dokhane A, Hennig D, Rizwan-uddin, Chawla R
    Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis
    Annals of Nuclear Energy. 2007; 34(4): 271-287. https://doi.org/10.1016/j.anucene.2006.12.005
    DORA PSI
  • Macian R, Zimmermann MA, Chawla R
    Statistical uncertainty analysis applied to fuel depletion calculations
    Journal of Nuclear Science and Technology. 2007; 44(6): 875-885. https://doi.org/10.3327/jnst.44.875
    DORA PSI
  • Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja OP, et al.
    Radial and azimuthal 235U fission and 238U capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements
    Nuclear Science and Engineering. 2007; 155(1): 96-101. https://doi.org/10.13182/NSE07-A2647
    DORA PSI
  • Mikityuk K, Coddington P, Pelloni S, Bubelis E, Chawla R
    Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic–cooled reactor systems
    Nuclear Technology. 2007; 157(1): 18-36. https://doi.org/10.13182/NT07-A3799
    DORA PSI
  • Petkevich P, Mikityuk K, Coddington P, Chawla R
    Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel
    Annals of Nuclear Energy. 2007; 34(9): 707-718. https://doi.org/10.1016/j.anucene.2007.03.009
    DORA PSI
  • Romano A, Horvath MI, Restani R
    Evolution of porosity in the high-burnup fuel structure
    Journal of Nuclear Materials. 2007; 361(1): 62-68. https://doi.org/10.1016/j.jnucmat.2006.09.016
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
    Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data
    Annals of Nuclear Energy. 2007; 34(8): 615-627. https://doi.org/10.1016/j.anucene.2007.02.020
    DORA PSI
  • Vinai P, Macian-Juan R, Chawla R
    A statistical methodology for quantification of uncertainty in best estimate code physical models
    Annals of Nuclear Energy. 2007; 34(8): 628-640. https://doi.org/10.1016/j.anucene.2007.03.003
    DORA PSI
  • Zerkak O, Coddington P, Eitschberger H
    Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
    Nuclear Engineering and Design. 2007; 237(11): 1195-1208. https://doi.org/10.1016/j.nucengdes.2007.01.011
    DORA PSI
  • Barten W, Coddington P, Ferroukhi H
    RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
    Annals of Nuclear Energy. 2006; 33(2): 99-118. https://doi.org/10.1016/j.anucene.2005.09.011
    DORA PSI
  • Bergmann UC, Chawla R, Jatuff F, Murphy MF
    Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 556(1): 331-338. https://doi.org/10.1016/j.nima.2005.08.110
    DORA PSI
  • Blair P, Romano A, Hellwig C, Chawla R
    Calculations on fission gas behaviour in the high burnup structure
    Journal of Nuclear Materials. 2006; 350(3): 232-239. https://doi.org/10.1016/j.jnucmat.2006.01.006
    DORA PSI
  • Dokhane A, Ferroukhi H, Zimmermann MA, Aguirre C
    Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation
    Annals of Nuclear Energy. 2006; 33(16): 1329-1338. https://doi.org/10.1016/j.anucene.2006.08.010
    DORA PSI
  • Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, et al.
    Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
    Journal of Nuclear Science and Technology. 2006; 43(3): 223-230. https://doi.org/10.3327/jnst.43.223
    DORA PSI
  • Jatuff F, Giust F, Krouthén J, Helmersson S, Chawla R
    Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly
    Annals of Nuclear Energy. 2006; 33(2): 119-125. https://doi.org/10.1016/j.anucene.2005.09.007
    DORA PSI
  • Jatuff F, Macku K, Chawla R
    On the accuracy of reactor physics calculations for square HPLWR fuel assemblies
    Annals of Nuclear Energy. 2006; 33(2): 198-207. https://doi.org/10.1016/j.anucene.2005.09.006
    DORA PSI
  • Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten H-J, et al.
    HTGR reactor physics and fuel cycle studies
    Nuclear Engineering and Design. 2006; 236(5-6): 615-634. https://doi.org/10.1016/j.nucengdes.2005.10.021
    DORA PSI
  • Lucas D, Krepper E, Prasser H-M, Manera A
    Investigations on the stability of the flow characteristics in a bubble column
    Chemical Engineering and Technology. 2006; 29(9): 1066-1072. https://doi.org/10.1002/ceat.200600150
    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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2001 - 2004

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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2000 and before

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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