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:
 

  • Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
    Iterative Bayesian Monte Carlo for nuclear data evaluation
    Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
    DORA PSI
  • Alyammahi N, Yoon HJ, Al-Yahia OS, Leung R
    The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
    Nuclear Engineering and Design. 2022; 397: 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
    DORA PSI
  • Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
    Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
    European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
    DORA PSI
  • Cozzo C, Khvostov G, Clifford I, Ferroukhi H
    Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
    Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
    DORA PSI
  • Di Giuli M, Malicki M, Dejardin P, Corda V, Swaidan AM
    MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
    Nuclear Engineering and Design. 2022; 387: 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248
    DORA PSI
  • Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
    Development of a more accurate dynamic bias error model for two-phase flow measurements performed with radiation transmission
    International Journal of Multiphase Flow. 2022; 146: 103881 (22 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103881
    DORA PSI
  • Dokhane A, Vasiliev A, Hursin M, Rochman D, Ferroukhi H
    A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
    Nuclear Engineering and Technology. 2022; 54(5): 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
    DORA PSI
  • Dokhane A, Vasiliev A, Ferroukhi H
    On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999
    Nuclear Engineering and Design. 2022; 399: 112016 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112016
    DORA PSI
  • Doll U, Migliorini M, Baikie J, Zachos PK, Röhle I, Melnikov S, et al.
    Non-intrusive flow diagnostics for unsteady inlet flow distortion measurements in novel aircraft architectures
    Progress in Aerospace Sciences. 2022; 130: 100810 (24 pp.). https://doi.org/10.1016/j.paerosci.2022.100810
    DORA PSI
  • Doll U, Röhle I, Dues M, Kapulla R
    Time-resolved multi-parameter flow diagnostics by filtered Rayleigh scattering: system design through multi-objective optimisation
    Measurement Science and Technology. 2022; 33(10): 105204 (12 pp.). https://doi.org/10.1088/1361-6501/ac7cca
    DORA PSI
  • Downing JR, Petrov V, Manera A
    3D field data of flow structures in dead-ended, coolant loop reactor branch lines for CFD validation of thermal fatigue onset modeling
    Nuclear Engineering and Design. 2022; 399: 112012 (10 pp.). https://doi.org/10.1016/j.nucengdes.2022.112012
    DORA PSI
  • Fagnoni F, Konarski P
    Hydrogen degassing of zirconium under high-vacuum conditions
    Metals. 2022; 12(5): 868 (9 pp.). https://doi.org/10.3390/met12050868
    DORA PSI
  • Fiorina C, Clifford I, Kelm S, Lorenzi S
    On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
    Nuclear Engineering and Design. 2022; 387: 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
    DORA PSI
  • Fogliatto EO, Clausse A, Teruel FE
    Development of a double-MRT pseudopotential model for tridimensional boiling simulation
    International Journal of Thermal Sciences. 2022; 179: 107637 (13 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107637
    DORA PSI
  • Janasz F, Prasser H-M, Suckow D, Mityakov A
    The use of a novel gradient heat flux sensor for characterization of reflux condensation
    Nuclear Engineering and Design. 2022; 395: 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885
    DORA PSI
  • Jang J, Hursin M, Lee W, Pautz A, Papadionysiou M, Ferroukhi H, et al.
    Analysis of Rostov-II benchmark using conventional two-step code systems
    Energies. 2022; 15(9): 3318 (24 pp.). https://doi.org/10.3390/en15093318
    DORA PSI
  • Jansson P, Bengtsson M, Bäckström U, Álvarez-Velarde F, Čalič D, Caruso S, et al.
    Blind benchmark exercise for spent nuclear fuel decay heat
    Nuclear Science and Engineering. 2022; 196(9): 1125-1145. https://doi.org/10.1080/00295639.2022.2053489
    DORA PSI
  • Kalilainen J, Lind T
    Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
    Annals of Nuclear Energy. 2022; 166: 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740
    DORA PSI
  • Kapulla R, Paranjape S, Doll U, Kirkby E, Paladino D
    Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
    Nuclear Engineering and Technology. 2022; 54(11): 4348-4358. https://doi.org/10.1016/j.net.2022.07.001
    DORA PSI
  • Kapulla R, Doll U, Kirkby E, Paranjape S, Paladino D
    Growth laws and self-similarity in the confined mixing zone of unstratified and strongly stably stratified isokinetic mixing-layers past a splitter plate
    Physics of Fluids. 2022; 34(3): 035129 (16 pp.). https://doi.org/10.1063/5.0082950
    DORA PSI
  • Kapulla R, Paranjape S, Fehlmann M, Suter S, Doll U, Paladino D
    The effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility
    Nuclear Engineering and Technology. 2022; 54(6): 2311-2320. https://doi.org/10.1016/j.net.2021.12.032
    DORA PSI
  • Khvostov G
    Modelling effects of transient FGR in LWR fuel rods during a LOCA
    Journal of Nuclear Materials. 2022; 559: 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
    DORA PSI
  • Maestre J, Bahamonde C, Lamas Garcia I, Kershaw K, Biancacci N, Busom J, et al.
    High intensity proton beam impact at 440 GeV/c on Mo and Cu coated CfC/graphite and SiC/SiC absorbers for beam intercepting devices
    Journal of Instrumentation. 2022; 17: P01019 (32 pp.). https://doi.org/10.1088/1748-0221/17/01/P01019
    DORA PSI
  • Mager T, Fiorina C, Hursin M, Pautz A
    Investigation and validation of unstructured mesh methodologies for modeling experimental reactors
    Energies. 2022; 15(4): 1512 (11 pp.). https://doi.org/10.3390/en15041512
    DORA PSI
  • Mao J, Petrov V, Manera A, Howard TK, Cetiner SM
    On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
    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
  • 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. 2022. https://doi.org/10.1080/00295639.2022.2103344
    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
  • Viernstein A, Kubicek M, Morgenbesser M, Huber TM, Ellmeyer E, Siebenhofer M, et al.
    Mechanism of photo-ionic stoichiometry changes in SrTiO3
    Solid State Ionics. 2022; 383: 115992 (9 pp.). https://doi.org/10.1016/j.ssi.2022.115992
    DORA PSI
  • Vijayakumar J, Gaspar M, Maurel L, Horisberger M, Nolting F, Vaz CAF
    High frequency characterization of Si3 N4 dielectrics for artificial magnetoelectric devices
    Journal of Materials Science. 2022; 57: 19872-19881. https://doi.org/10.1007/s10853-022-07832-2
    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: (14 pp.). https://doi.org/10.1016/j.net.2022.07.009
    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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  • 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
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  • Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
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    Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
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    Data assimilation of post-irradiation examination data for fission yields from GEF
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    On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
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    Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
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    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
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  • 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
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  • Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
    A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
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    Statistical burnup distribution of moving pebbles in the HTR-PM reactor
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  • 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
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  • Andreani M, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, Herranz LE, et al.
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    Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
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    The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
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  • Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
    Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
    Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
    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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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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  • 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
  • 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
  • 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
  • Kapulla R, Mignot G, Paranjape S, Ryan L, Paladino D
    Large scale gas stratification erosion by a vertical helium-air jet
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    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
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  • 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
  • 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
  • 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
  • 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
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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. https://doi.org/10.1155/2012/158617
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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. https://doi.org/10.1155/2012/746467
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  • 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. https://doi.org/10.1155/2012/239319
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • Revents F, Pérez M, 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. https://doi.org/10.1155/2010/219294
    DORA PSI
  • 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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Operation Conditions Of A Phase Doppler Anemometer: Droplet Size Measurements With Laser Beam Power, Photomultiplier Voltage, Signal Gain And Signal-To-Noisle Ratio As Parameters
R Kapulla, SB Najera
Measurement Science & Technology 17, 221-227 (2006).
http://dx.doi.org/10.1088/0957-0233/17/1/034

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

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

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

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

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

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


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

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

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

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

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


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


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

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


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


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


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

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

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

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

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

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

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


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

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

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

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

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

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

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

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

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

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

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


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


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

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

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

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

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

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

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

 

 

 

 

 

 

 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

 

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Research Division
Nuclear Energy and Safety (NES)

Laboratory for Reactor Physics and Thermal-Hydraulics (LRT)
Paul Scherrer Institute
5232 Villigen PSI
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Hakim Ferroukhi
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