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:
 

2024

  • Al-Yahia OS, Clifford I, Ferroukhi H
    Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility
    Nuclear Engineering and Technology. 2024. https://doi.org/10.1016/j.net.2024.02.050
    DORA PSI
  • Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
    The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions
    Nuclear Engineering and Design. 2024; 416: 112815 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112815
    DORA PSI
  • Albà A, Adelmann A, Münster L, Rochman D, Boiger R
    Fast uncertainty quantification of spent nuclear fuel with neural networks
    Annals of Nuclear Energy. 2024; 196: 110204 (8 pp.). https://doi.org/10.1016/j.anucene.2023.110204
    DORA PSI
  • Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Rada AP, et al.
    A segmented total energy detector (sTED) optimized for (n, γ) cross-section measurements at n_TOF EAR2
    Radiation Physics and Chemistry. 2024; 217: 111525 (11 pp.). https://doi.org/10.1016/j.radphyschem.2024.111525
    DORA PSI
  • Amaducci S, Colonna N, Cosentino L, Cristallo S, Finocchiaro P, Krtička M, et al.
    Measurement of the Ce 140 (n,γ) cross section at n_TOF and its astrophysical implications for the chemical evolution of the universe
    Physical Review Letters. 2024; 132(12): 122701 (8 pp.). https://doi.org/10.1103/PhysRevLett.132.122701
    DORA PSI
  • Araujo DM, Auchmann B, Brem A, Daly M, Hug C, Michlmayr T, et al.
    Assessment of training performance, degradation and robustness of paraffin-wax impregnated Nb3Sn demonstrator under high magnetic field
    IEEE Transactions on Applied Superconductivity. 2024; 34(5): 7000208 (8 pp.). https://doi.org/10.1109/TASC.2024.3368995
    DORA PSI
  • Baccou J, Glantz T, Ghione A, Sargentini L, Fillion P, Damblin G, et al.
    A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
    Nuclear Engineering and Design. 2024; 421: 113035 (16 pp.). https://doi.org/10.1016/j.nucengdes.2024.113035
    DORA PSI
  • Balibrea-Correa J, Lerendegui-Marco J, Babiano-Suarez V, Domingo-Pardo C, Ladarescu I, Tarifeño-Saldivia A, et al.
    Pushing the high count rate limits of scintillation detectors for challenging neutron-capture experiments
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2024; 1064: 169385 (13 pp.). https://doi.org/10.1016/j.nima.2024.169385
    DORA PSI
  • Berry L, Vasiliev A, Hursin M, Rochman D, Frankl M, Ferroukhi H
    Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions
    Progress in Nuclear Energy. 2024; 172: 105203 (16 pp.). https://doi.org/10.1016/j.pnucene.2024.105203
    DORA PSI
  • Bersano A, Lombardo C, Alblouwy F, Karppinen I, Silde A, Nikitin K, et al.
    Benchmark exercise on ELSMOR passive heat removal system
    Nuclear Engineering and Design. 2024; 419: 112961 (14 pp.). https://doi.org/10.1016/j.nucengdes.2024.112961
    DORA PSI
  • Brem A, Duda M, Müller C, Garcia H, Hug C, Daly M, et al.
    From hot to cold: advanced materials and processes for Nb3Sn based magnets
    IEEE Transactions on Applied Superconductivity. 2024; 34(5): 7700105 (5 pp.). https://doi.org/10.1109/TASC.2023.3338588
    DORA PSI
  • Butcher TA, Phillips NW, Chiu CC, Wei CC, Ho SZ, Chen YC, et al.
    Ptychographic nanoscale imaging of the magnetoelectric coupling in freestanding BiFeO3
    Advanced Materials. 2024: 2311157 (6 pp.). https://doi.org/10.1002/adma.202311157
    DORA PSI
  • Chae MS, Kelm S, Paladino D
    Analyses of International Standard Problem ISP-47 TOSQAN experiment with containmentFOAM
    Nuclear Engineering and Technology. 2024; 56(2): 611-623. https://doi.org/10.1016/j.net.2023.10.038
    DORA PSI
  • Cherezov A, Vasiliev A, Ferroukhi H
    Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method
    Annals of Nuclear Energy. 2024; 206: 110575 (11 pp.). https://doi.org/10.1016/j.anucene.2024.110575
    DORA PSI
  • Constantinou P, Stock TJZ, Tseng LT, Kazazis D, Muntwiler M, Vaz CAF, et al.
    EUV-induced hydrogen desorption as a step towards large-scale silicon quantum device patterning
    Nature Communications. 2024; 15(1): 694 (13 pp.). https://doi.org/10.1038/s41467-024-44790-6
    DORA PSI
  • Coppo Leite V, Merzari E, Mao J, Petrov V, Manera A
    High-fidelity simulation of mixing phenomena in large enclosures
    Nuclear Science and Engineering. 2024; 198(7): 1386-1403. https://doi.org/10.1080/00295639.2023.2186159
    DORA PSI
  • Darby FB, Pakari OV, Hua MY, Lamirand V, Clarke SD, Pautz A, et al.
    Neutron-gamma noise measurements in a zero-power reactor using organic scintillators
    IEEE Transactions on Nuclear Science. 2024; 71(5): 1033-1040. https://doi.org/10.1109/TNS.2023.3337657
    DORA PSI
  • Dehbi A, Kapulla R
    CFD simulations of helium layer erosion in one PANDA vessel following cooler activation
    Nuclear Engineering and Design. 2024; 422: 113154 (14 pp.). https://doi.org/10.1016/j.nucengdes.2024.113154
    DORA PSI
  • Doll U, Kapulla R, Dues M, Steinbock J, Melnikov S, Röhle I, et al.
    Towards time-resolved multi-property measurements by filtered Rayleigh scattering: diagnostic approach and verification
    Experiments in Fluids. 2024; 65(1): 2 (13 pp.). https://doi.org/10.1007/s00348-023-03740-6
    DORA PSI
  • D’Ambrosi V, Sercombe J, Bejaoui S, Chaieb A, Baurens B, Largenton R, et al.
    P2M simulation exercise on past fuel melting irradiation experiments
    Nuclear Technology. 2024; 210(2): 189-2015. https://doi.org/10.1080/00295450.2023.2194270
    DORA PSI
  • Ekahana SA, Soh Y, Tamai A, Gosálbez-Martínez D, Yao M, Hunter A, et al.
    Anomalous electrons in a metallic kagome ferromagnet
    Nature. 2024; 627(8002): 67-72. https://doi.org/10.1038/s41586-024-07085-w
    DORA PSI
  • Fagnoni F, Kursun E.C, Busi M, Konarski P, Yetik O, Spolenak R, et al.
    Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation
    Journal of Nuclear Materials. 2024; 590: 154873 (10 pp.). https://doi.org/10.1016/j.jnucmat.2023.154873
    DORA PSI
  • Faldella F, Eisenring S, Kim T, Doll U, Jansohn P
    Turbulent flame speed and flame characteristics of lean premixed H2-CH4 flames at moderate pressure levels
    Journal of Engineering for Gas Turbines and Power. 2024; 146(2): 021012 (8 pp.). https://doi.org/10.1115/1.4063524
    DORA PSI
  • Grasso M, Petrov V, Manera A
    Accuracy and error analysis of optical liquid film thickness measurement with total internal reflection method (TIRM)
    Experiments in Fluids. 2024; 65(6): 83 (17 pp.). https://doi.org/10.1007/s00348-024-03820-1
    DORA PSI
  • Huang P-H, Ahn T, Manera A, Petrov V
    Investigation of key parameters for the operation of a sodium heat pipe with visualization using X-ray radiography
    Applied Thermal Engineering. 2024; 236: 121867 (12 pp.). https://doi.org/10.1016/j.applthermaleng.2023.121867
    DORA PSI
  • Hursin M, Vasiliev A, Rochman D, Dokhane A, Ferroukhi H
    Monte Carlo analysis of BWR geometries using a cycle check-up methodology
    Annals of Nuclear Energy. 2024; 195: 110170 (17 pp.). https://doi.org/10.1016/j.anucene.2023.110170
    DORA PSI
  • Kapulla R, Kelm S, Doll U, Liu X, Paranjape S, Paladino D
    Large-scale PANDA facility – radiation experiments and CFD calculations
    Kerntechnik. 2024. https://doi.org/10.1515/kern-2023-0060
    DORA PSI
  • Kim T, Doll U, Faldella F, Jansohn P
    Quantification of mixing quality effects on flashback limits for H2-rich fuel gases in lean premixed combustion using laser-induced fluorescence of acetone
    Journal of Engineering for Gas Turbines and Power. 2024; 146(7): 071004 (7 pp.). https://doi.org/10.1115/1.4064359
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Development and testing of the hydrogen behavior tool for Falcon - HYPE
    Nuclear Engineering and Technology. 2024; 56(2): 728-744. https://doi.org/10.1016/j.net.2023.11.012
    DORA PSI
  • Kristian A, Richard H, Pascal V, Braillard O, Manera A, Petrov V
    An NEA/OECD benchmark-experiment for the validation of CFD for mixing and thermal fatigue in T-junction dead leg flows
    Nuclear Engineering and Design. 2024; 417: 112813 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112813
    DORA PSI
  • Ligonnet T, Laureau A, Simbsler P, Pautz A, Lamirand V
    Design of an open-loop pile-oscillation program in the CROCUS reactor
    IEEE Transactions on Nuclear Science. 2024; 71(5): 1001-1009. https://doi.org/10.1109/TNS.2024.3371183
    DORA PSI
  • Mao J, Che S, Petrov V, Manera A
    Benchmark experiments for turbulent mixing in the scaled-down upper plenum of high-temperature gas-cooled reactors under accident scenario
    Nuclear Science and Engineering. 2024; 198(7): 1371-1385. https://doi.org/10.1080/00295639.2023.2186726
    DORA PSI
  • Mao J, Manera A, Petrov V
    High-resolution experiments for mixing in large enclosures
    Nuclear Engineering and Design. 2024; 417: 112828 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112828
    DORA PSI
  • Mao J, Vishwakarma V, Welker Z, Tai CK, Bolotnov IA, Petrov V, et al.
    Validation of RANS-based turbulence models against high-resolution experiments and DNS for buoyancy-driven flow with stratified fronts
    Nuclear Science and Engineering. 2024; 198(7): 1404-1425. https://doi.org/10.1080/00295639.2023.2241800
    DORA PSI
  • Mascari F, Bersano A, Massone M, Agnello G, Coindreau O, Beck S, et al.
    Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
    Annals of Nuclear Energy. 2024; 196: 110205 (14 pp.). https://doi.org/10.1016/j.anucene.2023.110205
    DORA PSI
  • Nikitin K, Clifford I, Ferroukhi H
    Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
    Annals of Nuclear Energy. 2024; 195: 110147 (12 pp.). https://doi.org/10.1016/j.anucene.2023.110147
    DORA PSI
  • Pakari O, Mager T, Frajtag P, Pautz A, Lamirand V
    Gamma noise to non-invasively monitor nuclear research reactors
    Scientific Reports. 2024; 14(1): 8409 (10 pp.). https://doi.org/10.1038/s41598-024-59127-y
    DORA PSI
  • Paranjape S, Kapulla R, Kudinov P, Chae MS, Paladino D
    Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection
    Nuclear Engineering and Design. 2024; 419: 112914 (17 pp.). https://doi.org/10.1016/j.nucengdes.2024.112914
    DORA PSI
  • Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
    Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique
    Journal of Aerosol Science. 2024; 178: 106336 (17 pp.). https://doi.org/10.1016/j.jaerosci.2024.106336
    DORA PSI
  • Reventos F, D'Auria F, Herranz L, Sanchez Perea M, Carlos Alberola S, Freixa J, et al.
    What is the future for nuclear fission technology? A technical opinion from the guest editors of VSI NFT series and the editor of the Journal Nuclear Engineering and Design
    Nuclear Engineering and Design. 2024; 425: 113332 (11 pp.). https://doi.org/10.1016/j.nucengdes.2024.113332
    DORA PSI
  • Tagliente G, Milazzo PM, Paradela C, Kopecky S, Vescovi D, Alaerts G, et al.
    High-resolution cross section measurements for neutron interactions on 89Y with incident neutron energies up to 95 keV
    European Physical Journal A: Hadrons and Nuclei. 2024; 60(1): 21 (18 pp.). https://doi.org/10.1140/epja/s10050-024-01243-4
    DORA PSI
  • Tai CK, Mao J, Petrov V, Manera A, Bolotnov IA
    Study of stable stratification in HiRJET facility with direct numerical simulation
    Nuclear Science and Engineering. 2024; 198(7): 1347-1370. https://doi.org/10.1080/00295639.2023.2197656
    DORA PSI

2023

  • Aboljadayel ROM, Kinane CJ, Vaz CAF, Love DM, Martin M-B, Cabrero-Vilatela A, et al.
    Measurement of the induced magnetic polarisation of rotated-domain graphene grown on Co film with polarised neutron reflectivity
    Nanomaterials. 2023; 13(19): 2620 (11 pp.). https://doi.org/10.3390/nano13192620
    DORA PSI
  • Ahn T, Diaz J, Adams R, Petrov V, Manera A
    Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
    Nuclear Technology. 2023; 209: 1898-1913. https://doi.org/10.1080/00295450.2023.2197680
    DORA PSI
  • Al-Yahia OS, Clifford I, Bissels W-M, Suckow D, Ferroukhi H
    Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
    Nuclear Engineering and Design. 2023; 405: 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224
    DORA PSI
  • Al-Yahia OS, Clifford I, Nikitin K, Liu P, Ferroukhi H
    TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
    Nuclear Engineering and Design. 2023; 406: 112234 (21 pp.). https://doi.org/10.1016/j.nucengdes.2023.112234
    DORA PSI
  • Alhassan E, Rochman D, Vasiliev A, Koning AJ, Ferroukhi H
    TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV
    Applied Radiation and Isotopes. 2023; 198: 110832 (15 pp.). https://doi.org/10.1016/j.apradiso.2023.110832
    DORA PSI
  • Auchmann B, Araujo DM, Brem A, Daly M, Felder R, Feuvrier J, et al.
    Test results from CD1 Short CCT Nb3Sn dipole demonstrator and considerations about CCT technology for the FCC-hh main dipole
    IEEE Transactions on Applied Superconductivity. 2023; 34(5): 4000906 (6 pp.). https://doi.org/10.1109/TASC.2023.3344425
    DORA PSI
  • Berry L, Truchet G, Bonaccorsi T
    Accelerated Monte Carlo perturbation calculation by surface recovery
    Annals of Nuclear Energy. 2023; 185: 109716 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109716
    DORA PSI
  • Bourdot Dutra C da S, Merzari E, Acierno J, Kraus A, Manera A, Petrov V, et al.
    High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors
    Nuclear Technology. 2023; 209: 1592-1616. https://doi.org/10.1080/00295450.2023.2181040
    DORA PSI
  • Breitenmoser D, Prasser HM, Manera A, Petrov V
    Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography
    International Journal of Multiphase Flow. 2023; 161: 104382 (10 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2023.104382
    DORA PSI
  • Cavaliere A, Marone F, Cozzo C, Buchanan K, Lorrette C, Pouchon MA
    FEM heat transfer modelling with tomography-based SiCf/SiC unit cell
    High Temperatures-High Pressures. 2023; 52(2): 95-110. https://doi.org/10.32908/hthp.v52.1281
    DORA PSI
  • Cherezov A, Vasiliev A, Ferroukhi H
    Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic
    Applied Sciences. 2023; 13(2): 896 (14 pp.). https://doi.org/10.3390/app13020896
    DORA PSI
  • Coindreau O, Herranz LE, Bocanegra R, Ederli S, Maccari P, Mascari F, et al.
    Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
    Annals of Nuclear Energy. 2023; 188: 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
    DORA PSI
  • Dehbi A, Kapulla R
    CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
    Nuclear Engineering and Design. 2023; 415: 112710 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112710
    DORA PSI
  • Diaz J, Liu Q, Petrov V, Manera A, Sun X
    High-resolution X-Ray radiography methods developed for Post-CHF experiment
    Nuclear Technology. 2023; 209(10): 1442-1465. https://doi.org/10.1080/00295450.2022.2133504
    DORA PSI
  • Dokhane A, Vasiliev A, Hursin M, Ferroukhi H
    Nuclear data effect on BWR stability parameter uncertainty at stable core conditions
    Nuclear Engineering and Design. 2023; 414: 112620 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112620
    DORA PSI
  • 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
  • Garbil R, Hadj Hassine SB, Blaise P, Ferry C, Sjöland A, Christensen P, et al.
    Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
    EPJ Nuclear Sciences and Technologies. 2023; 9: 2022029 (12 pp.). https://doi.org/10.1051/epjn/2022029
    DORA PSI
  • Gonzalez-Amoros J, Papadionysiou M, Kim S, Joo HG
    Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis
    Nuclear Science and Engineering. 2023; 197(8): 1634-1655. https://doi.org/10.1080/00295639.2022.2140577
    DORA PSI
  • Gupta S, Herranz LE, Lebel LS, Sonnenkalb M, Pellegrini M, Marchetto C, et al.
    Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
    Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
    DORA PSI
  • Hursin M, Zoia A, Rouchon A, Brighenti A, Zmijarevic I, Santandrea S, et al.
    Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
    Annals of Nuclear Energy. 2023; 194: 110066 (16 pp.). https://doi.org/10.1016/j.anucene.2023.110066
    DORA PSI
  • Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
    A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes
    Annals of Nuclear Energy. 2023; 189: 109842 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109842
    DORA PSI
  • Jäckel BS, Birchley JC, Lind T, Steinbrück M, Park S
    Nitriding model for zirconium based fuel cladding in severe accident codes
    Journal of Nuclear Materials. 2023; 582: 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
    DORA PSI
  • Kang S, Huang PH, Petrov V, Manera A, Ahn T, Kammenzind B, et al.
    Determination of the hydrogen heat of transport in Zircaloy-4
    Journal of Nuclear Materials. 2023; 573: 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
    DORA PSI
  • Kapulla R, Xiongguo L, Kelm S, Doll U, Paranjape S, Paladino D
    Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations
    Nuclear Engineering and Design. 2023; 411: 112408 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112408
    DORA PSI
  • Khvostov G
    Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX
    Journal of Nuclear Materials. 2023; 584: 154589 (8 pp.). https://doi.org/10.1016/j.jnucmat.2023.154589
    DORA PSI
  • Khvostov G
    Calibration and validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX
    Journal of Nuclear Materials. 2023; 584: 154588 (11 pp.). https://doi.org/10.1016/j.jnucmat.2023.154588
    DORA PSI
  • Khvostov G
    Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment
    Nuclear Engineering and Technology. 2023; 55(10): 3801-3807. https://doi.org/10.1016/j.net.2023.06.045
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Modeling of hydrogen behavior in liner claddings
    Journal of Nuclear Materials. 2023; 573: 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
    DORA PSI
  • Krempaský J, Springholz G, D'Souza SW, Caha O, Gmitra M, Ney A, et al.
    Efficient magnetic switching in a correlated spin glass
    Nature Communications. 2023; 14(1): 6127 (11 pp.). https://doi.org/10.1038/s41467-023-41718-4
    DORA PSI
  • Laureau A, Gruel A, Lamirand V, Ligonnet T, Sardet A, Pautz A
    Analysis of the preliminary campaign for the PETALE program
    EPJ Nuclear Sciences and Technologies. 2023; 9: 25 (9 pp.). https://doi.org/10.1051/epjn/2023010
    DORA PSI
  • Lee H, Vasiliev A, Ferroukhi H
    Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
    Annals of Nuclear Energy. 2023; 181: 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556
    DORA PSI
  • Malicki M, Lind T
    Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation
    Nuclear Engineering and Technology. 2023; 55(7): 2504-2515. https://doi.org/10.1016/j.net.2023.04.003
    DORA PSI
  • Malicki M, Lind T
    Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
    Progress in Nuclear Energy. 2023; 158: 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
    DORA PSI
  • Mao J, Petrov V, Manera A, Howard TK, Cetiner SM
    On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
    Nuclear Technology. 2023; 209(10). https://doi.org/10.1080/00295450.2022.2133505
    DORA PSI
  • Mascari F, Bersano A, Adorni M, D'Ovidio G, Martín-Fuertes F, Jin XZ, et al.
    Current status of MELCOR 2.2 for fusion safety analyses
    Fusion Engineering and Design. 2023; 194: 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869
    DORA PSI
  • Michalopoulou V, Stamatopoulos A, Diakaki M, Tsinganis A, Vlastou R, Kokkoris M, et al.
    Measurement of the neutron-induced fission cross section of 230Th at the CERN n_TOF facility
    Physical Review C: Nuclear Physics. 2023; 108(1): 014616 (15 pp.). https://doi.org/10.1103/PhysRevC.108.014616
    DORA PSI
  • Miniero L, Pandey K, Fredrich D, Shcherbanev S, Doll U, Giusti A, et al.
    Air-blast atomization and ignition of a kerosene spray in hot vitiated crossflow
    Combustion and Flame. 2023; 256: 112915 (13 pp.). https://doi.org/10.1016/j.combustflame.2023.112915
    DORA PSI
  • Müller A, Okur F, Aribia A, Osenciat N, Vaz CAF, Siller V, et al.
    Benchmarking the performance of lithiated metal oxide interlayers at the LiCoO2|LLZO interface
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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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    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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    Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
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    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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    Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
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    Investigation on the effect of eccentricity for fuel disc irradiation tests
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    Development and application of marginal likelihood optimization for integral parameter adjustment
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    Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
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    Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator
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    Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
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    Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
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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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    Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
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    Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
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    On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
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    Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
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    Calibration technique and sample measurement database for material decomposition imaging using a compact deuterium-deuterium (D-D) fast neutron generator
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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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  • 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

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

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

  • 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/10.1080/18811248.2009.9711602
    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, 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
  • 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/10.1080/18811248.2008.9711424
    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
  • Blanchet D, Huot N, Sireta P, Serviere H, Boyard M, Antony M, et al.
    Qualification of a gamma-ray heating calculation scheme for the future Jules Horowitz material testing reactor (RJH)
    Annals of Nuclear Energy. 2008; 35(4): 731-745. https://doi.org/10.1016/j.anucene.2007.07.021
    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
  • Lebrat JF, Aliberti G, D'Angelo A, Billebaud A, Brissot R, Brockmann H, et al.
    Global results from deterministic and stochastic analysis of the MUSE-4 experiments on the neutronics of accelerator-driven systems
    Nuclear Science and Engineering. 2008; 158(1): 49-67. https://doi.org/10.13182/NSE05-100
    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
  • Bart G, Bakker K, Hellwig C, Kihara Y, Ozawa T, Wallin H, et al.
    Fuji, an initial sintering comparison test for pelletized-, sphere-pac-and vipac-fast breeder reactor mixed oxide fuel
    Journal of Nuclear Science and Technology. 2007; 44(3): 329-336. https://doi.org/10.1080/18811248.2007.9711290
    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
  • Milenković RŽ, Sigg B, Yadigaroglu G
    Bubble clustering and trapping in large vortices. Part 1: triggered bubbly jets investigated by phase-averaging
    International Journal of Multiphase Flow. 2007; 33(10): 1088-1110. https://doi.org/10.1016/j.ijmultiphaseflow.2007.05.003
    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
  • Stoenescu R, Schaeublin R, Gavillet D, Baluc N
    Mechanical properties-microstructure correlation in neutron irradiated heat-affected zones of austenitic stainless steels
    Journal of Nuclear Materials. 2007; 362(2-3): 287-292. https://doi.org/10.1016/j.jnucmat.2007.01.251
    DORA PSI
  • Stoenescu R, Schäublin R, Gavillet D, Baluc N
    Welding-induced mechanical properties in austenitic stainless steels before and after neutron irradiation
    Journal of Nuclear Materials. 2007; 360(3): 255-264. https://doi.org/10.1016/j.jnucmat.2006.10.009
    DORA PSI
  • Stoenescu R, Schäublin R, Gavillet D, Baluc N
    Welding-induced microstructure in austenitic stainless steels before and after neutron irradiation
    Journal of Nuclear Materials. 2007; 360(2): 186-195. https://doi.org/10.1016/j.jnucmat.2006.10.007
    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/10.1080/18811248.2006.9711084
    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
  • Jasiulevičius A, Sehgal BR
    Experimental investigation of debris bed quenching with non-condensable gas release
    Energetika. 2006; 3(1): 1-8.
    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

 

 

 

 

 

 

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

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