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

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

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

2023

  • Al-Yahia OS, Clifford I, Bissels W-M, Suckow D, Ferroukhi H
    Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
    Nuclear Engineering and Design. 2023; 405: 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224
    DORA PSI
  • Al-Yahia OS, Clifford I, Nikitin K, Liu P, Ferroukhi H
    TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
    Nuclear Engineering and Design. 2023; 406: 112234 (21 pp.). https://doi.org/10.1016/j.nucengdes.2023.112234
    DORA PSI
  • Breitenmoser D, Prasser HM, Manera A, Petrov V
    Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography
    International Journal of Multiphase Flow. 2023; 161: 104382 (10 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2023.104382
    DORA PSI
  • Cherezov A, Vasiliev A, Ferroukhi H
    Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic
    Applied Sciences. 2023; 13(2): 896 (14 pp.). https://doi.org/10.3390/app13020896
    DORA PSI
  • Coindreau O, Herranz LE, Bocanegra R, Ederli S, Maccari P, Mascari F, et al.
    Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
    Annals of Nuclear Energy. 2023; 188: 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
    DORA PSI
  • Diaz J, Liu Q, Petrov V, Manera A, Sun X
    High-resolution X-Ray radiography methods developed for Post-CHF experiment
    Nuclear Technology. 2023. https://doi.org/10.1080/00295450.2022.2133504
    DORA PSI
  • Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
    Advances and new ideas for neutron-capture astrophysics experiments at CERN n_TOF
    European Physical Journal A: Hadrons and Nuclei. 2023; 59(1): 8 (11 pp.). https://doi.org/10.1140/epja/s10050-022-00876-7
    DORA PSI
  • Fogliatto E, Puragliesi R, Clifford I, Ferroukhi H
    Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
    Annals of Nuclear Energy. 2023; 185: 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715
    DORA PSI
  • Frankl M, Wittel M, Diomidis N, Vasiliev A, Ferroukhi H, Pudollek S
    Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository
    Annals of Nuclear Energy. 2023; 180: 109449 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109449
    DORA PSI
  • Gupta S, Herranz LE, Lebel LS, Sonnenkalb M, Pellegrini M, Marchetto C, et al.
    Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
    Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
    DORA PSI
  • Kang S, Huang PH, Petrov V, Manera A, Ahn T, Kammenzind B, et al.
    Determination of the hydrogen heat of transport in Zircaloy-4
    Journal of Nuclear Materials. 2023; 573: 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Modeling of hydrogen behavior in liner claddings
    Journal of Nuclear Materials. 2023; 573: 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
    DORA PSI
  • Lee H, Vasiliev A, Ferroukhi H
    Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
    Annals of Nuclear Energy. 2023; 181: 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556
    DORA PSI
  • Malicki M, Lind T
    Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
    Progress in Nuclear Energy. 2023; 158: 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
    DORA PSI
  • Paladino D, Kapulla R, Paranjape S, Suter S, Hug C, Chae M-S, et al.
    PANDA experimental database and further needs for containment analyses
    Nuclear Engineering and Design. 2023; 404: 112173 (18 pp.). https://doi.org/10.1016/j.nucengdes.2023.112173
    DORA PSI
  • Pelloni S, Rochman D
    Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region
    Annals of Nuclear Energy. 2023; 182: 109603 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109603
    DORA PSI
  • Rochman DA, Álvarez-Velarde F, Dagan R, Fiorito L, Häkkinen S, Kromar M, et al.
    On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
    EPJ Nuclear Sciences and Technologies. 2023; 9: 14 (24 pp.). https://doi.org/10.1051/epjn/2022055
    DORA PSI
  • Siefman D, Hursin M, Percher C, Heinrichs D
    Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws
    Nuclear Science and Engineering. 2023; 197: 14-24. https://doi.org/10.1080/00295639.2022.2103344
    DORA PSI
  • Vocke M, Kapulla R, Morton C, Klein M, Martinuzzi RJ
    Advection-based temporal reconstruction technique for turbulent velocity fields
    Physics of Fluids. 2023; 35(1): 015123 (18 pp.). https://doi.org/10.1063/5.0129564
    DORA PSI
  • Vázquez-Rodríguez C, Andreani M, Jiménez G, Kapulla R, Paranjape S, Manuel Martín-Valdepeñas J, et al.
    Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – simulations using GOTHIC8.3(QA)
    Nuclear Engineering and Design. 2023; 403: 112120 (20 pp.). https://doi.org/10.1016/j.nucengdes.2022.112120
    DORA PSI
  • Wolfertz A, Perret G, Adams R
    Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
    Annals of Nuclear Energy. 2023; 188: 109792 (10 pp.). https://doi.org/10.1016/j.anucene.2023.109792
    DORA PSI

 

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  • Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
    Iterative Bayesian Monte Carlo for nuclear data evaluation
    Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
    DORA PSI
  • Alyammahi N, Yoon HJ, Al-Yahia OS, Leung R
    The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
    Nuclear Engineering and Design. 2022; 397: 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
    DORA PSI
  • Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
    Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
    European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
    DORA PSI
  • Cozzo C, Khvostov G, Clifford I, Ferroukhi H
    Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
    Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
    DORA PSI
  • Di Giuli M, Malicki M, Dejardin P, Corda V, Swaidan AM
    MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
    Nuclear Engineering and Design. 2022; 387: 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248
    DORA PSI
  • Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
    Development of a more accurate dynamic bias error model for two-phase flow measurements performed with radiation transmission
    International Journal of Multiphase Flow. 2022; 146: 103881 (22 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103881
    DORA PSI
  • Dokhane A, Vasiliev A, Hursin M, Rochman D, Ferroukhi H
    A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
    Nuclear Engineering and Technology. 2022; 54(5): 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
    DORA PSI
  • Dokhane A, Vasiliev A, Ferroukhi H
    On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999
    Nuclear Engineering and Design. 2022; 399: 112016 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112016
    DORA PSI
  • Doll U, Migliorini M, Baikie J, Zachos PK, Röhle I, Melnikov S, et al.
    Non-intrusive flow diagnostics for unsteady inlet flow distortion measurements in novel aircraft architectures
    Progress in Aerospace Sciences. 2022; 130: 100810 (24 pp.). https://doi.org/10.1016/j.paerosci.2022.100810
    DORA PSI
  • Doll U, Röhle I, Dues M, Kapulla R
    Time-resolved multi-parameter flow diagnostics by filtered Rayleigh scattering: system design through multi-objective optimisation
    Measurement Science and Technology. 2022; 33(10): 105204 (12 pp.). https://doi.org/10.1088/1361-6501/ac7cca
    DORA PSI
  • Downing JR, Petrov V, Manera A
    3D field data of flow structures in dead-ended, coolant loop reactor branch lines for CFD validation of thermal fatigue onset modeling
    Nuclear Engineering and Design. 2022; 399: 112012 (10 pp.). https://doi.org/10.1016/j.nucengdes.2022.112012
    DORA PSI
  • Fagnoni F, Konarski P
    Hydrogen degassing of zirconium under high-vacuum conditions
    Metals. 2022; 12(5): 868 (9 pp.). https://doi.org/10.3390/met12050868
    DORA PSI
  • Fiorina C, Clifford I, Kelm S, Lorenzi S
    On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
    Nuclear Engineering and Design. 2022; 387: 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
    DORA PSI
  • Fogliatto EO, Clausse A, Teruel FE
    Development of a double-MRT pseudopotential model for tridimensional boiling simulation
    International Journal of Thermal Sciences. 2022; 179: 107637 (13 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107637
    DORA PSI
  • Gonzalez-Amoros J, Papadionysiou M, Kim S, Joo HG
    Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis
    Nuclear Science and Engineering. 2022. https://doi.org/10.1080/00295639.2022.2140577
    DORA PSI
  • Janasz F, Prasser H-M, Suckow D, Mityakov A
    The use of a novel gradient heat flux sensor for characterization of reflux condensation
    Nuclear Engineering and Design. 2022; 395: 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885
    DORA PSI
  • Jang J, Hursin M, Lee W, Pautz A, Papadionysiou M, Ferroukhi H, et al.
    Analysis of Rostov-II benchmark using conventional two-step code systems
    Energies. 2022; 15(9): 3318 (24 pp.). https://doi.org/10.3390/en15093318
    DORA PSI
  • Jansson P, Bengtsson M, Bäckström U, Álvarez-Velarde F, Čalič D, Caruso S, et al.
    Blind benchmark exercise for spent nuclear fuel decay heat
    Nuclear Science and Engineering. 2022; 196(9): 1125-1145. https://doi.org/10.1080/00295639.2022.2053489
    DORA PSI
  • Kalilainen J, Lind T
    Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
    Annals of Nuclear Energy. 2022; 166: 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740
    DORA PSI
  • Kapulla R, Paranjape S, Doll U, Kirkby E, Paladino D
    Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
    Nuclear Engineering and Technology. 2022; 54(11): 4348-4358. https://doi.org/10.1016/j.net.2022.07.001
    DORA PSI
  • Kapulla R, Doll U, Kirkby E, Paranjape S, Paladino D
    Growth laws and self-similarity in the confined mixing zone of unstratified and strongly stably stratified isokinetic mixing-layers past a splitter plate
    Physics of Fluids. 2022; 34(3): 035129 (16 pp.). https://doi.org/10.1063/5.0082950
    DORA PSI
  • Kapulla R, Paranjape S, Fehlmann M, Suter S, Doll U, Paladino D
    The effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility
    Nuclear Engineering and Technology. 2022; 54(6): 2311-2320. https://doi.org/10.1016/j.net.2021.12.032
    DORA PSI
  • Khvostov G
    Modelling effects of transient FGR in LWR fuel rods during a LOCA
    Journal of Nuclear Materials. 2022; 559: 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
    DORA PSI
  • Maestre J, Bahamonde C, Lamas Garcia I, Kershaw K, Biancacci N, Busom J, et al.
    High intensity proton beam impact at 440 GeV/c on Mo and Cu coated CfC/graphite and SiC/SiC absorbers for beam intercepting devices
    Journal of Instrumentation. 2022; 17: P01019 (32 pp.). https://doi.org/10.1088/1748-0221/17/01/P01019
    DORA PSI
  • Mager T, Fiorina C, Hursin M, Pautz A
    Investigation and validation of unstructured mesh methodologies for modeling experimental reactors
    Energies. 2022; 15(4): 1512 (11 pp.). https://doi.org/10.3390/en15041512
    DORA PSI
  • Mao J, Petrov V, Manera A, Howard TK, Cetiner SM
    On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
    Nuclear Technology. 2022. https://doi.org/10.1080/00295450.2022.2133505
    DORA PSI
  • Martinez-Quiroga V, Szogradi M, Schollenberger S, Sanchez-Perea M, Sandberg N, Zhongyun J, et al.
    OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
    Nuclear Engineering and Design. 2022; 389: 111632 (20 pp.). https://doi.org/10.1016/j.nucengdes.2021.111632
    DORA PSI
  • Moreno-Soto J, Valenta S, Berthoumieux E, Chebboubi A, Diakaki M, Dridi W, et al.
    Constraints on the dipole photon strength for the odd uranium isotopes
    Physical Review C: Nuclear Physics. 2022; 105(2): 024618 (14 pp.). https://doi.org/10.1103/PhysRevC.105.024618
    DORA PSI
  • Nichenko S, Kalilainen J, Lind T
    MSR simulation with cGEMS: fission product release and aerosol formation
    Journal of Nuclear Engineering. 2022; 3(1): 105-116. https://doi.org/10.3390/jne3010006
    DORA PSI
  • Nikitin K, Clifford I, Dokhane A, Ferroukhi H
    Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
    Nuclear Engineering and Design. 2022; 389: 111649 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.111649
    DORA PSI
  • Pakari OV, Lamirand V, Mager T, Frajtag P, Pautz A
    High accuracy measurement of the prompt neutron decay constant in CROCUS using gamma noise and bootstrapped uncertainties
    Annals of Nuclear Energy. 2022; 170: 109011 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109011
    DORA PSI
  • Paladino D, Kapulla R, Paranjape S, Suter S, Andreani M
    PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena
    Nuclear Engineering and Design. 2022; 392: 111777 (18 pp.). https://doi.org/10.1016/j.nucengdes.2022.111777
    DORA PSI
  • Paladino D, Paranjape S, Mignot G, Kapulla R
    Parametric study highlighting cooler and spray activation on the transient mixing of a three-gas composition in the PANDA facility
    Progress in Nuclear Energy. 2022; 150: 104283 (9 pp.). https://doi.org/10.1016/j.pnucene.2022.104283
    DORA PSI
  • Pandey K, Miniero L, Doll U, de Oliveira PM, Mastorakos E, Noiray N
    Topological transitions of Jet A-1 lean azimuthal flames (LEAF)
    Proceedings of the Combustion Institute. 2022. https://doi.org/10.1016/j.proci.2022.08.034
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs
    Nuclear Engineering and Design. 2022; 398: 111946 (16 pp.). https://doi.org/10.1016/j.nucengdes.2022.111946
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data
    Annals of Nuclear Energy. 2022; 178: 109385 (34 pp.). https://doi.org/10.1016/j.anucene.2022.109385
    DORA PSI
  • Papaoikonomou A, Wingate J, Verma V, Durrant A, Ioannou G, Papagiannis T, et al.
    Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements
    Annals of Nuclear Energy. 2022; 178: 109373 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109373
    DORA PSI
  • Pelloni S, Rochman D
    Adjustment of JEFF-3.3 data for U-235 and Pu-239 in the fast, non-resonant energy range
    Annals of Nuclear Energy. 2022; 177: 109296 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109296
    DORA PSI
  • Perret G, Wicaksono D, Clifford ID, Ferroukhi H
    Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
    Nuclear Technology. 2022; 208(4): 711-722. https://doi.org/10.1080/00295450.2021.1936879
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Muñoz A, Vazquez Antolin M, Berrios Torres M, et al.
    Analysis of ENRESA BWR samples: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2022; 8: 9 (16 pp.). https://doi.org/10.1051/epjn/2022007
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Koning A, Sublet J-C
    Impact of H in H2O thermal scattering data on criticality calculation: uncertainty and adjustment
    EPJ Nuclear Sciences and Technologies. 2022; 8: 3 (7 pp.). https://doi.org/10.1051/epjn/2021028
    DORA PSI
  • Scolaro A, Fiorina C, Clifford I, Pautz A
    Development of a semi-implicit contact methodology for finite volume stress solvers
    International Journal for Numerical Methods in Engineering. 2022; 123(2): 309-338. https://doi.org/10.1002/nme.6857
    DORA PSI
  • Scolaro A, Van Uffelen P, Schubert A, Fiorina C, Brunetto E, Clifford I, et al.
    Towards coupling conventional with high-fidelity fuel behavior analysis tools
    Progress in Nuclear Energy. 2022; 152: 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
    DORA PSI
  • Shama A, Rochman D, Caruso S, Pautz A
    Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
    Annals of Nuclear Energy. 2022; 165: 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758
    DORA PSI
  • Vidal-Ferràndiz A, Ginestar D, Carreño A, Verdú G, Dokhane A, Verma V, et al.
    Modelling and simulations of reactor neutron noise induced by mechanical vibrations
    Annals of Nuclear Energy. 2022; 177: 109300 (21 pp.). https://doi.org/10.1016/j.anucene.2022.109300
    DORA PSI
  • Ványi AS, Hursin M, Czifrus S
    Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors
    Annals of Nuclear Energy. 2022; 174: 109147 (11 pp.). https://doi.org/10.1016/j.anucene.2022.109147
    DORA PSI
  • Wei Z, Ničeno B, Puragliesi R, Fogliatto E
    Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
    Nuclear Engineering and Technology. 2022; 54(11): 4359-4372. https://doi.org/10.1016/j.net.2022.07.009
    DORA PSI
  • Welker Z, Manera A, Petrov V, Balestra P
    An experimental and theoretical examination of air ingress rates during small- and medium-break air ingress accidents
    Nuclear Technology. 2022: (15 pp.). https://doi.org/10.1080/00295450.2022.2134673
    DORA PSI
  • Yoon HJ, Alyammahi N, Al-Yahia OS, Leung R
    Validation of RELAP5 MOD3.3 for 1% reactor pressure vessel top head break loss of coolant accident via the ATLAS facility
    Nuclear Engineering and Design. 2022; 400: 112054 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.112054
    DORA PSI
  • Yum S, Hursin M, Vasiliev A, Vinai P, Mylonakis AG, Demazière C, et al.
    Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
    Annals of Nuclear Energy. 2022; 174: 109157 (13 pp.). https://doi.org/10.1016/j.anucene.2022.109157
    DORA PSI

 

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  • 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
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    FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
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    Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
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    Development, design, and testing of a microwave-driven compact rotating-target D-D fast neutron generator for imaging applications
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    Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
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    Delayed gamma fraction determination in the zero power reactor CROCUS
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    Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
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    Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
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    Sea container inspection with tagged neutrons
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    Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
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  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M
    Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
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    Impact of H in H2O thermal scattering data on depletion calculation: k∞, nuclide inventory and decay heat
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  • Rochman D, Shama A, Pudollek S, Caruso S, Pautz A
    Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
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  • Scolaro A, Van Uffelen P, Fiorina C, Schubert A, Clifford I, Pautz A
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  • Siefman D, Hursin M, Schnabel G, Sjöstrand H
    Development and application of marginal likelihood optimization for integral parameter adjustment
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  • Sobes V, de Saint Jean C, Rochman D, Cabellos O, Holcomb A, Bauge E, et al.
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  • 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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  • Soubelet B, Adams R, Prasser H-M
    Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator
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  • Stuckert J, Steinbrueck M, Kalilainen J, Lind T, Birchley J
    Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
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  • Torres Delgado LA, Verma V, Montalvo C, Dokhane A, García-Berrocal A
    Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
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  • Verma V, Chionis D, Dokhane A, Ferroukhi H
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  • Ványi AS, Babcsány B, Böröczki ZI, Horváth A, Hursin M, Szieberth M, et al.
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  • Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
    Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
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  • Andreani M, Kapulla R, Kelm S, Paladino D, Paranjape S
    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
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    Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
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    Development and verification of a methodology for neutron noise response to fuel assembly vibrations
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    Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
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    Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
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    Treatment of the implicit effect in Shark-X
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    Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
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    Evaporation of materials from the molten salt reactor fuel under elevated temperatures
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    Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
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    Analytical criteria for fuel fragmentation and burst FGR during a LOCA
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    Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
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  • Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D
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    Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
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    Uncertainty propagation based on correlated sampling technique for nuclear data applications
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    A summary of fission-product-transport phenomena during SGTR severe accidents
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    Assessment of nTRACER and PARCS performance for VVER configurations
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    Gas mixing caused by interacting heat sources PART I: experiments
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    Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
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    A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
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    Improvement of PIE analysis with a full core simulation: the U1 case
     
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    Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
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    Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
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    Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
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  • Sakellarakis VD, Vera-Tudela W, Doll U, Ebi D, Wright YM, Boulouchos K
    The effect of high-pressure injection variations on the mixing state of underexpanded methane jets
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    The OFFBEAT multi-dimensional fuel behavior solver
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    Anchoring of premixed jet flames in vitiated crossflow with pulsed nanosecond spark discharge
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  • Siefman D, Hursin M, Perret G, Pautz A
    Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
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  • Siefman D, Hursin M, Sjostrand H, Schnabel G, Rochman D, Pautz A
    Data assimilation of post-irradiation examination data for fission yields from GEF
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  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
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  • Solans V, Rochman D, Ferroukhi H, Vasiliev A, Pautz A
    Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
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  • Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 - results of severe accident analyses for unit 2
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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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    A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
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  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    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.
    Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
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    Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
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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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    Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
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  • Griffin PJ, Koning AJ, Rochman D
    Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
    IEEE Transactions on Nuclear Science. 2019; 66(7): 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
    DORA PSI
  • Hennig D, Lange C, Rizwan-uddin, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
    Progress in Nuclear Energy. 2019; 115: 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
    DORA PSI
  • Hennig D, Rizwan-uddin, Lange C, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
    Progress in Nuclear Energy. 2019; 113: 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
    DORA PSI
  • Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
    The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
    Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
    DORA PSI
  • Koning AJ, Rochman D, Sublet J-C, Dzysiuk N, Fleming M, van der Marck S
    TENDL: complete nuclear data library for innovative nuclear science and technology
    Nuclear Data Sheets. 2019; 155: 1-55. https://doi.org/10.1016/j.nds.2019.01.002
    DORA PSI
  • Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
    Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
    Applied Radiation and Isotopes. 2019; 145: 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
    DORA PSI
  • Lind T, Guentay S, Herranz LE, Suckow D
    A summary of the ARTIST: aerosol retention during SGTR severe accident
    Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
    DORA PSI
  • Nikitin K, Mueller P, Bruder A, Walser S, Judd J, Hiltbrand D
    BWR-4 ATWS modeling with RELAP5-S3K
    Nuclear Engineering and Design. 2019; 344: 38-45. https://doi.org/10.1016/j.nucengdes.2019.01.023
    DORA PSI
  • Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
    Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
    Nuclear Technology. 2019; 205(1-2): 153-173. https://doi.org/10.1080/00295450.2018.1505356
    DORA PSI
  • Paranjape S, Mignot G, Kapulla R, Paladino D
    Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
    Nuclear Engineering and Design. 2019; 342: 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017
    DORA PSI
  • Park J, Kim W, Hursin M, Perret G, Vasiliev A, Rochman D, et al.
    Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
    Annals of Nuclear Energy. 2019; 131: 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
    DORA PSI
  • Pecchia M, Ferroukhi H, Vasiliev A, Grimm P
    Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
    Annals of Nuclear Energy. 2019; 129: 67-78. https://doi.org/10.1016/j.anucene.2019.01.047
    DORA PSI
  • Pelloni S, Rochman D
    Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
    Annals of Nuclear Energy. 2019; 129: 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
    DORA PSI
  • Perret G, Wicaksono D, Clifford ID, Ferroukhi H
    Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
    Nuclear Technology. 2019; 205(12): 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Pelloni S, Bauge E, Koning A
    Correlation ν̅ p – σ for U-Pu in the thermal and resonance neutron range via integral information
    European Physical Journal Plus. 2019; 134: 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
    DORA PSI
  • Shama A, Pouchon MA, Clifford I
    Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
    Additive Manufacturing. 2019; 26: 1-14. https://doi.org/10.1016/j.addma.2018.12.011
    DORA PSI
  • Skorek T, de Crécy A, Kovtonyuk A, Petruzzi A, Mendizábal R, de Alfonso E, et al.
    Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
    Nuclear Engineering and Design. 2019; 354: 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
    DORA PSI
  • Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
    Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
    Radiation Physics and Chemistry. 2019; 156: 292-299. https://doi.org/10.1016/j.radphyschem.2018.11.017
    DORA PSI
  • Sublet J-C, Bondarenko IP, Bonny G, Conlin JL, Gilbert MR, Greenwood LR, et al.
    Neutron-induced damage simulations: beyond defect production cross-section, displacement per atom and iron-based metrics
    European Physical Journal Plus. 2019; 134(7): 350 (50 pp.). https://doi.org/10.1140/epjp/i2019-12758-y
    DORA PSI
  • Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
    Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
    Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
    DORA PSI
  • Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
    Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
    Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
    DORA PSI
  • Vasiliev A, Herrero J, Pecchia M, Rochman D, Ferroukhi H, Caruso S
    Preliminary assessment of criticality safety constraints for swiss spent nuclear fuel loading in disposal canisters
    Materials. 2019; 12(3): 494 (30 pp.). https://doi.org/10.3390/ma12030494
    DORA PSI
  • Yang J, Suckow D, Lind T, Prasser H-M
    Study of level swell for a Filtered Containment Venting System at the VEFITA facility
    Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
    DORA PSI

 

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

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

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

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

 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

 

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  • Bertolotto D, Manera A, Frey S, Prasser H-M, Chawla R
    Single-phase mixing studies by means of a directly coupled CFD/system-code tool
    Annals of Nuclear Energy. 2009; 36(3): 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
    DORA PSI
  • Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
    First-principles study of crystalline and amorphous Ge2Sb2Te5 and the effects of stoichiometric defects
    Journal of Physics: Condensed Matter. 2009; 21(25): 255501 (14 pp.). https://doi.org/10.1088/0953-8984/21/25/255501
    DORA PSI
  • Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
    Unravelling the mechanism of pressure induced amorphization of phase change materials
    Physical Review Letters. 2009; 102(20): 205502 (4 pp.). https://doi.org/10.1103/PhysRevLett.102.205502
    DORA PSI
  • Caruso S, Murphy MF, Jatuff F, Chawla R
    Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography
    Nuclear Engineering and Design. 2009; 239(7): 1220-1228. https://doi.org/10.1016/j.nucengdes.2009.02.019
    DORA PSI
  • Chawla R
    Editorial
    Annals of Nuclear Energy. 2009; 36(3): 255-257. https://doi.org/10.1016/j.anucene.2008.11.008
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions
    Nuclear Engineering and Design. 2009; 239(11): 2417-2429. https://doi.org/10.1016/j.nucengdes.2009.07.015
    DORA PSI
  • Cucinotta CS, Miceli G, Raiteri P, Krack M, Kühne TD, Bernasconi M, et al.
    Superionic conduction in substoichiometric LiAl alloy: an Ab Initio study
    Physical Review Letters. 2009; 103(12): 125901 (4 pp.). https://doi.org/10.1103/PhysRevLett.103.125901
    DORA PSI
  • Ferroukhi H, Zerkak O, Chawla R
    Cross-section modelling effects on pressurised water reactor main steam line break analyses
    Annals of Nuclear Energy. 2009; 36(8): 1184-1200. https://doi.org/10.1016/j.anucene.2009.04.006
    DORA PSI
  • Ferroukhi H, Hollard JM, Zimmermann MA, Chawla R
    Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme
    Annals of Nuclear Energy. 2009; 36(3): 286-291. https://doi.org/10.1016/j.anucene.2008.12.010
    DORA PSI
  • Ferroukhi H, Zimmermann MA
    Study of the PWR REA pulse width for realistic UO2 and MOX core designs using 3D kinetics methods
    Annals of Nuclear Energy. 2009; 36(8): 1170-1183. https://doi.org/10.1016/j.anucene.2009.04.007
    DORA PSI
  • Jatuff F, Perret G, Murphy MF, Giust F, Chawla R
    Void reactivity coefficient benchmark results for a 10 × 10 BWR assembly in the full 0-100% void fraction range
    Annals of Nuclear Energy. 2009; 36(6): 853-858. https://doi.org/10.1016/j.anucene.2009.02.013
    DORA PSI
  • Kato Y, Tsuzuki N, Nikitin K, Ishizuka T
    Advanced microchannel heat exchanger with S-shaped fins
    Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.1080/18811248.2007.9711547
    DORA PSI
  • Krepel J, Pelloni S, Mikityuk K, Coddington P
    EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
    Annals of Nuclear Energy. 2009; 36(5): 550-561. https://doi.org/10.1016/j.anucene.2009.01.008
    DORA PSI
  • Kühne TD, Krack M, Parrinello M
    Static and dynamical properties of liquid water from first principles by a novel Car-Parrinello-like approach
    Journal of Chemical Theory and Computation. 2009; 5(2): 235-241. https://doi.org/10.1021/ct800417q
    DORA PSI
  • Liu L-M, Krack M, Michaelides A
    Interfacial water: a first principles molecular dynamics study of a nanoscale water film on salt
    Journal of Chemical Physics. 2009; 130(23): 234702 (12 pp.). https://doi.org/10.1063/1.3152845
    DORA PSI
  • Manera A, Ozar B, Paranjape S, Ishii M, Prasser H-M
    Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
    Nuclear Engineering and Design. 2009; 239(9): 1718-1724. https://doi.org/10.1016/j.nucengdes.2008.06.015
    DORA PSI
  • Mikityuk K
    Heat transfer to liquid metal: review of data and correlations for tube bundles
    Nuclear Engineering and Design. 2009; 239(4): 680-687. https://doi.org/10.1016/j.nucengdes.2008.12.014
    DORA PSI
  • Perret G, Murphy MF, Jatuff F, Sublet JC, Bouland O, Chawla R
    Impact of new gadolinium cross sections on reaction rate distributions in 10×10 BWR assemblies
    Nuclear Science and Engineering. 2009; 163(1): 17-25. https://doi.org/10.13182/NSE08-55
    DORA PSI
  • Petkevich P, Mikityuk K, Coddington P, Chawla R
    Development and benchmarking of a mechanical model for GFR plate-type fuel
    Annals of Nuclear Energy. 2009; 36(8): 1262-1269. https://doi.org/10.1016/j.anucene.2009.01.015
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
    Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.3327/jnst.46.933
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
    Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.1080/18811248.2009.9711602
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Perret G, Seiler R, Chawla R
    Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model
    Annals of Nuclear Energy. 2009; 36(10): 1536-1543. https://doi.org/10.1016/j.anucene.2009.07.012
    DORA PSI
  • Romano A, Shuffler CA, Garkisch HD, Olander DR, Todreas NE
    Fuel performance analysis for PWR cores
    Nuclear Engineering and Design. 2009; 239(8): 1481-1488. https://doi.org/10.1016/j.nucengdes.2008.11.022
    DORA PSI
  • Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
    Gas cooled fast reactor research and development in the European Union
    Science and Technology of Nuclear Installations. 2009; 2009: 238624 (7 pp.). https://doi.org/10.1155/2009/238624
    DORA PSI
  • Tsuzuki N, Kato Y, Nikitin K, Ishizuka T
    Advanced microchannel heat exchanger with S-shaped fins
    Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.3327/jnst.46.403
    DORA PSI
  • Aounallah Y
    A separate-effect-based new appraisal of convective boiling and its suppression
    Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.3327/jnst.45.149
    DORA PSI
  • Barten W, Jasiulevicius A, Manera A, Macian-Juan R, Zerkak O
    Analysis of the capability of system codes to model cavitation water hammers: simulation of UMSICHT water hammer experiments with TRACE and RELAP5
    Nuclear Engineering and Design. 2008; 238(4): 1129-1145. https://doi.org/10.1016/j.nucengdes.2007.10.004
    DORA PSI
  • Barten W, Manera A, Macian-Juan R
    One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
    Nuclear Engineering and Design. 2008; 238(10): 2568-2582. https://doi.org/10.1016/j.nucengdes.2008.05.004
    DORA PSI
  • Blair P, Khvostov G, Romano A, Hellwig C, Chawla R
    Interpretation of high-burnup fuel annealing tests
    Journal of Nuclear Science and Technology. 2008; 45(7): 639-646. https://doi.org/10.1080/18811248.2008.9711463
    DORA PSI
  • Bubelis E, Castelliti D, Coddington P, Dor I, Fouillet C, de Geus E, et al.
    A GFR benchmark: comparison of transient analysis codes based on the ETDR concept
    Progress in Nuclear Energy. 2008; 50(1): 37-51. https://doi.org/10.1016/j.pnucene.2007.11.090
    DORA PSI
  • Bubelis E, Coddington P, Mikityuk K
    Verification of the TRACE code against the MEGAPIE transient data
    Annals of Nuclear Energy. 2008; 35(7): 1284-1295. https://doi.org/10.1016/j.anucene.2007.12.006
    DORA PSI
  • Caruso S, Günther-Leopold I, Murphy MF, Jatuff F, Chawla R
    Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2008; 589(3): 425-435. https://doi.org/10.1016/j.nima.2008.03.005
    DORA PSI
  • Caruso S, Murphy MF, Jatuff F, Chawla R
    Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography
    Journal of Nuclear Science and Technology. 2008; 45(8): 828-835. https://doi.org/10.3327/jnst.45.828
    DORA PSI
  • Chawla R, Jatuff F, Tani F
    Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice
    Annals of Nuclear Energy. 2008; 35(3): 495-502. https://doi.org/10.1016/j.anucene.2007.06.027
    DORA PSI
  • Cometto M, Wydler P, Chawla R
    Management of actinide waste inventories in nuclear phase-out scenarios
    Annals of Nuclear Energy. 2008; 35(8): 1447-1460. https://doi.org/10.1016/j.anucene.2008.01.016
    DORA PSI
  • Girardin G, Rimpault G, Morin F, Bosq JC, Coddington P, Mikityuk K, et al.
    Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
    Annals of Nuclear Energy. 2008; 35(12): 2206-2218. https://doi.org/10.1016/j.anucene.2008.09.008
    DORA PSI
  • Kolbe E, Vasiliev A, Ferroukhi H, Zimmermann MA
    Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems
    Annals of Nuclear Energy. 2008; 35(10): 1831-1841. https://doi.org/10.1016/j.anucene.2008.04.009
    DORA PSI
  • Kosa M, Krack M, Cheetham AK, Parrinello M
    Modeling the hydrogen storage materials with exposed M2+ coordination sites
    Journal of Physical Chemistry C. 2008; 112(42): 16171-16173. https://doi.org/10.1021/jp806394g
    DORA PSI
  • Krepel J, Rohde U, Grundmann U, Weiss F-P
    Dynamics of molten salt reactors
    Nuclear Technology. 2008; 164(1): 34-44. https://doi.org/10.13182/NT08-A4006
    DORA PSI
  • Liu L, Krack M, Michaelides A
    Density oscillations in a nanoscale water film on salt: insight from ab initio molecular dynamics
    Journal of the American Chemical Society. 2008; 130(27): 8572-8573. https://doi.org/10.1021/ja8014296
    DORA PSI
  • Mikityuk K, Coddington P, Gröschel F
    Analysis of radioactivity releases in the MEGAPIE reference accident
    Nuclear Engineering and Design. 2008; 238(7): 1838-1844. https://doi.org/10.1016/j.nucengdes.2007.12.004
    DORA PSI
  • Murphy MF, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
    Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions
    Annals of Nuclear Energy. 2008; 35(11): 2042-2050. https://doi.org/10.1016/j.anucene.2008.06.001
    DORA PSI
  • Perret G, Plaschy M, Murphy MF, Jatuff F, Chawla R
    Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly
    Annals of Nuclear Energy. 2008; 35(3): 478-484. https://doi.org/10.1016/j.anucene.2007.06.025
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
    On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test
    Annals of Nuclear Energy. 2008; 35(4): 565-569. https://doi.org/10.1016/j.anucene.2007.08.018
    DORA PSI
  • Vasiliev A, Kolbe E, Ferroukhi H, Zimmermann MA, Chawla R
    On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
    Annals of Nuclear Energy. 2008; 35(12): 2432-2435. https://doi.org/10.1016/j.anucene.2008.07.009
    DORA PSI
  • Vasiliev A, Kolbe E, Zimmermann MA
    Towards the development of upper subcriticality limits on the basis of benchmark criticality calculations
    Annals of Nuclear Energy. 2008; 35(9): 1764-1773. https://doi.org/10.1016/j.anucene.2008.01.017
    DORA PSI
  • Bergmann UC, Grimm P, Jatuff F, Murphy MF, Chawla R
    Investigations of 238U captures to total fissions in a Westinghouse SVEA-96+ assembly
    Nuclear Science and Engineering. 2007; 156(1): 86-95. https://doi.org/10.13182/NSE07-A2687
    DORA PSI
  • Caruso S, Murphy M, Jatuff F, Chawla R
    Validation of of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel
    Annals of Nuclear Energy. 2007; 34(1-2): 28-35. https://doi.org/10.1016/j.anucene.2006.11.009
    DORA PSI
  • Dokhane A, Hennig D, Rizwan-uddin, Chawla R
    BWR stability and bifurcation analysis using reduced order models and system codes: identification of a subcritical Hopf bifurcation using RAMONA
    Annals of Nuclear Energy. 2007; 34(10): 792-802. https://doi.org/10.1016/j.anucene.2007.04.003
    DORA PSI
  • Dokhane A, Hennig D, Rizwan-uddin, Chawla R
    Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis
    Annals of Nuclear Energy. 2007; 34(4): 271-287. https://doi.org/10.1016/j.anucene.2006.12.005
    DORA PSI
  • Macian R, Zimmermann MA, Chawla R
    Statistical uncertainty analysis applied to fuel depletion calculations
    Journal of Nuclear Science and Technology. 2007; 44(6): 875-885. https://doi.org/10.3327/jnst.44.875
    DORA PSI
  • Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja OP, et al.
    Radial and azimuthal 235U fission and 238U capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements
    Nuclear Science and Engineering. 2007; 155(1): 96-101. https://doi.org/10.13182/NSE07-A2647
    DORA PSI
  • Mikityuk K, Coddington P, Pelloni S, Bubelis E, Chawla R
    Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic–cooled reactor systems
    Nuclear Technology. 2007; 157(1): 18-36. https://doi.org/10.13182/NT07-A3799
    DORA PSI
  • Petkevich P, Mikityuk K, Coddington P, Chawla R
    Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel
    Annals of Nuclear Energy. 2007; 34(9): 707-718. https://doi.org/10.1016/j.anucene.2007.03.009
    DORA PSI
  • Romano A, Horvath MI, Restani R
    Evolution of porosity in the high-burnup fuel structure
    Journal of Nuclear Materials. 2007; 361(1): 62-68. https://doi.org/10.1016/j.jnucmat.2006.09.016
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
    Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data
    Annals of Nuclear Energy. 2007; 34(8): 615-627. https://doi.org/10.1016/j.anucene.2007.02.020
    DORA PSI
  • Vinai P, Macian-Juan R, Chawla R
    A statistical methodology for quantification of uncertainty in best estimate code physical models
    Annals of Nuclear Energy. 2007; 34(8): 628-640. https://doi.org/10.1016/j.anucene.2007.03.003
    DORA PSI
  • Zerkak O, Coddington P, Eitschberger H
    Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
    Nuclear Engineering and Design. 2007; 237(11): 1195-1208. https://doi.org/10.1016/j.nucengdes.2007.01.011
    DORA PSI
  • Barten W, Coddington P, Ferroukhi H
    RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
    Annals of Nuclear Energy. 2006; 33(2): 99-118. https://doi.org/10.1016/j.anucene.2005.09.011
    DORA PSI
  • Bergmann UC, Chawla R, Jatuff F, Murphy MF
    Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 556(1): 331-338. https://doi.org/10.1016/j.nima.2005.08.110
    DORA PSI
  • Blair P, Romano A, Hellwig C, Chawla R
    Calculations on fission gas behaviour in the high burnup structure
    Journal of Nuclear Materials. 2006; 350(3): 232-239. https://doi.org/10.1016/j.jnucmat.2006.01.006
    DORA PSI
  • Dokhane A, Ferroukhi H, Zimmermann MA, Aguirre C
    Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation
    Annals of Nuclear Energy. 2006; 33(16): 1329-1338. https://doi.org/10.1016/j.anucene.2006.08.010
    DORA PSI
  • Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, et al.
    Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
    Journal of Nuclear Science and Technology. 2006; 43(3): 223-230. https://doi.org/10.3327/jnst.43.223
    DORA PSI
  • Jatuff F, Giust F, Krouthén J, Helmersson S, Chawla R
    Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly
    Annals of Nuclear Energy. 2006; 33(2): 119-125. https://doi.org/10.1016/j.anucene.2005.09.007
    DORA PSI
  • Jatuff F, Macku K, Chawla R
    On the accuracy of reactor physics calculations for square HPLWR fuel assemblies
    Annals of Nuclear Energy. 2006; 33(2): 198-207. https://doi.org/10.1016/j.anucene.2005.09.006
    DORA PSI
  • Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten H-J, et al.
    HTGR reactor physics and fuel cycle studies
    Nuclear Engineering and Design. 2006; 236(5-6): 615-634. https://doi.org/10.1016/j.nucengdes.2005.10.021
    DORA PSI
  • Lucas D, Krepper E, Prasser H-M, Manera A
    Investigations on the stability of the flow characteristics in a bubble column
    Chemical Engineering and Technology. 2006; 29(9): 1066-1072. https://doi.org/10.1002/ceat.200600150
    DORA PSI
  • Ma W, Bubelis E, Karbojian A, Sehgal BR, Coddington P
    Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis
    Nuclear Engineering and Design. 2006; 236(13): 1422-1444. https://doi.org/10.1016/j.nucengdes.2006.01.006
    DORA PSI
  • Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
    Advanced foil activation techniques for the measurement of within-pin distributions of the 63Cu(n,γ)64Cu reaction rate in nuclear fuel
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 562(1): 393-400. https://doi.org/10.1016/j.nima.2006.03.004
    DORA PSI
  • Mikityuk K, Coddington P, Bubelis E, Chawla R
    Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
    Nuclear Engineering and Design. 2006; 236(23): 2452-2473. https://doi.org/10.1016/j.nucengdes.2006.03.012
    DORA PSI
  • Murphy MF, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, et al.
    Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples
    Annals of Nuclear Energy. 2006; 33(9): 760-765. https://doi.org/10.1016/j.anucene.2006.04.003
    DORA PSI
  • Paratte JM, Früh R, Kasemeyer U, Kalugin MA, Timm W, Chawla R
    A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor
    Annals of Nuclear Energy. 2006; 33(8): 739-748. https://doi.org/10.1016/j.anucene.2005.09.012
    DORA PSI
  • Pelloni S, Bubelis E, Mikityuk K, Coddington P
    Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast
    Annals of Nuclear Energy. 2006; 33(6): 499-509. https://doi.org/10.1016/j.anucene.2006.01.002
    DORA PSI
  • Pelloni S, Coddington P
    On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores
    Annals of Nuclear Energy. 2006; 33(17-18): 1360-1367. https://doi.org/10.1016/j.anucene.2006.10.001
    DORA PSI
  • Plaschy M, Jatuff F, Grimm P, Tani F, Jacot-Guillarmod R, Giust F, et al.
    Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
    Journal of Nuclear Science and Technology. 2006; 43(11): 1298-1310. https://doi.org/10.3327/jnst.43.1298
    DORA PSI
  • Romano A, Li J, Yip S
    Atomistic simulation of rapid compression of fractured silicon carbide
    Journal of Nuclear Materials. 2006; 352(1-3): 22-28. https://doi.org/10.1016/j.jnucmat.2006.02.038
    DORA PSI
  • Romano A, Wallin H, Zimmermann MA, Chawla R
    Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
    Nuclear Engineering and Design. 2006; 236(3): 284-294. https://doi.org/10.1016/j.nucengdes.2005.08.007
    DORA PSI
  • Tani F, Jatuff F, Chawla R
    Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly
    Annals of Nuclear Energy. 2006; 33(6): 490-498. https://doi.org/10.1016/j.anucene.2006.02.005
    DORA PSI
  • Wenger HU, Al Mazouzi A, Atchison F, Burghartz M, Chawla R, Günther-Leopold I, et al.
    Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry
    Nuclear Physics A. 2006; 764: 1-14. https://doi.org/10.1016/j.nuclphysa.2005.08.023
    DORA PSI
  • Zilio VO, Joneja OP, Popowski Y, Rosenfeld A, Chawla R
    Absolute depth-dose-rate measurements for an 192Ir HDR brachytherapy source in water using MOSFET detectors
    Medical Physics. 2006; 33(6): 1532-1539. https://doi.org/10.1118/1.2198168
    DORA PSI

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

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

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

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

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

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

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


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

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

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

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

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


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


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

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


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


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


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

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

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

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

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

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

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


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

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

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

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

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

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

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

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

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

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

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


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


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

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

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

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

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

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

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

 

 

 

 

 

 

 

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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
Switzerland

Hakim Ferroukhi
Head of the Laboratory
Office: OHSA/C10
Telephone: +41 56 310 4062
E-mail: hakim.ferroukhi@psi.ch

Petra Kull
Administration and Assistance
Office: OHSA/C18
Telephone: + 41 56 310 2685
E-mail: petra.kull@psi.ch

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Current job openings in the Research Division for Nuclear Energy and Safety

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