Journal publications of the STARS Program

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

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

  • Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
    Iterative Bayesian Monte Carlo for nuclear data evaluation
    Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
    DORA PSI
  • Alyammahi N, Yoon HJ, Al-Yahia OS, Leung R
    The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
    Nuclear Engineering and Design. 2022; 397: 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
    DORA PSI
  • Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
    Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
    European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
    DORA PSI
  • Cozzo C, Khvostov G, Clifford I, Ferroukhi H
    Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
    Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
    DORA PSI
  • 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
  • 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
  • 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
  • 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
  • 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
  • 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
  • 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, Koning A, Sublet J-C
    Impact of H in H2O thermal scattering data on criticality calculation: uncertainty and adjustment
    EPJ Nuclear Sciences and Technologies. 2022; 8: 3 (7 pp.). https://doi.org/10.1051/epjn/2021028
    DORA PSI
  • Scolaro A, Fiorina C, Clifford I, Pautz A
    Development of a semi-implicit contact methodology for finite volume stress solvers
    International Journal for Numerical Methods in Engineering. 2022; 123(2): 309-338. https://doi.org/10.1002/nme.6857
    DORA PSI
  • Scolaro A, Van Uffelen P, Schubert A, Fiorina C, Brunetto E, Clifford I, et al.
    Towards coupling conventional with high-fidelity fuel behavior analysis tools
    Progress in Nuclear Energy. 2022; 152: 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
    DORA PSI
  • Shama A, Rochman D, Caruso S, Pautz A
    Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
    Annals of Nuclear Energy. 2022; 165: 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758
    DORA PSI
  • Siefman D, Hursin M, Percher C, Heinrichs D
    Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws
    Nuclear Science and Engineering. 2022. https://doi.org/10.1080/00295639.2022.2103344
    DORA PSI
  • Vidal-Ferràndiz A, Ginestar D, Carreño A, Verdú G, Dokhane A, Verma V, et al.
    Modelling and simulations of reactor neutron noise induced by mechanical vibrations
    Annals of Nuclear Energy. 2022; 177: 109300 (21 pp.). https://doi.org/10.1016/j.anucene.2022.109300
    DORA PSI
  • Ványi AS, Hursin M, Czifrus S
    Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors
    Annals of Nuclear Energy. 2022; 174: 109147 (11 pp.). https://doi.org/10.1016/j.anucene.2022.109147
    DORA PSI
  • Wei Z, Ničeno B, Puragliesi R, Fogliatto E
    Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
    Nuclear Engineering and Technology. 2022: (14 pp.). https://doi.org/10.1016/j.net.2022.07.009
    DORA PSI
  • 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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  • 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
  • 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
  • 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
  • Khvostov G, Gorzel A
    FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
    Nuclear Engineering and Technology. 2021; 53(11): 3741-3758. https://doi.org/10.1016/j.net.2021.06.001
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
    Journal of Nuclear Materials. 2021; 555: 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
    DORA PSI
  • Pelloni S, Rochman D
    Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
    Annals of Nuclear Energy. 2021; 163: 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
    DORA PSI
  • Pázsit I, Torres LA, Hursin M, Nylén H, Dykin V, Montalvo C
    Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
    Progress in Nuclear Energy. 2021; 138: 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
    DORA PSI
  • Pérot B, Carasco C, Eléon C, Bernard S, Sardet A, El Kanawati W, et al.
    Sea container inspection with tagged neutrons
    EPJ Nuclear Sciences and Technologies. 2021; 7: 6 (37 pp.). https://doi.org/10.1051/epjn/2021004
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M
    Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 18 (24 pp.). https://doi.org/10.1051/epjn/2021017
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M
    Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
    Annals of Nuclear Energy. 2021; 160: 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Hursin M, Ichou R, Taforeau J, et al.
    Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 14 (24 pp.). https://doi.org/10.1051/epjn/2021013
    DORA PSI
  • Rochman DA, Bauge E
    Fission yields and cross sections: correlated or not?
    EPJ Nuclear Sciences and Technologies. 2021; 7: 5 (9 pp.). https://doi.org/10.1051/epjn/2021005
    DORA PSI
  • Rochman D, Hursin M, Vasiliev A, Ferroukhi H
    Impact of H in H2O thermal scattering data on depletion calculation: k∞, nuclide inventory and decay heat
    EPJ Nuclear Sciences and Technologies. 2021; 7: 24 (8 pp.). https://doi.org/10.1051/epjn/2021027
    DORA PSI
  • Rochman D, Shama A, Pudollek S, Caruso S, Pautz A
    Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
    Nuclear Engineering and Technology. 2021; 53(9): 2816-2829. https://doi.org/10.1016/j.net.2021.03.013
    DORA PSI
  • Schnabel G, Sjöstrand H, Hansson J, Rochman D, Koning A, Capote R
    Conception and software implementation of a nuclear data evaluation pipeline
    Nuclear Data Sheets. 2021; 173: 239-284. https://doi.org/10.1016/j.nds.2021.04.007
    DORA PSI
  • Scolaro A, Van Uffelen P, Fiorina C, Schubert A, Clifford I, Pautz A
    Investigation on the effect of eccentricity for fuel disc irradiation tests
    Nuclear Engineering and Technology. 2021; 53(5): 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
    DORA PSI
  • Siefman D, Hursin M, Schnabel G, Sjöstrand H
    Development and application of marginal likelihood optimization for integral parameter adjustment
    Annals of Nuclear Energy. 2021; 159: 108255 (10 pp.). https://doi.org/10.1016/j.anucene.2021.108255
    DORA PSI
  • Sobes V, de Saint Jean C, Rochman D, Cabellos O, Holcomb A, Bauge E, et al.
    WPEC Subgroup 44 computational inter-comparison exercise on correlations in nuclear data libraries
    Annals of Nuclear Energy. 2021; 164: 108605 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108605
    DORA PSI
  • Solans V, Rochman D, Brazell C, Vasiliev A, Ferroukhi H, Pautz A
    Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
    Neural Computing & Applications. 2021; 33: 16627-16639. https://doi.org/10.1007/s00521-021-06258-2
    DORA PSI
  • Torres Delgado LA, Verma V, Montalvo C, Dokhane A, García-Berrocal A
    Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
    Nuclear Engineering and Design. 2021; 373: 111017 (18 pp.). https://doi.org/10.1016/j.nucengdes.2020.111017
    DORA PSI
  • Verma V, Chionis D, Dokhane A, Ferroukhi H
    Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
    Annals of Nuclear Energy. 2021; 157: 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
    DORA PSI
  • Ványi AS, Babcsány B, Böröczki ZI, Horváth A, Hursin M, Szieberth M, et al.
    Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
    Annals of Nuclear Energy. 2021; 155: 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
    DORA PSI

 

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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
    Annals of Nuclear Energy. 2020; 139: 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
    DORA PSI
  • Chionis D, Dokhane A, Belblidia L, Ferroukhi H, Girardin G, Pautz A
    Development and verification of a methodology for neutron noise response to fuel assembly vibrations
    Annals of Nuclear Energy. 2020; 147: 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
    DORA PSI
  • Fiorina C, Scolaro A, Siefman D, Hursin M, Pautz A
    Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
    Journal of Nuclear Engineering. 2020; 1(1): 54-62. https://doi.org/10.3390/jne1010005
    DORA PSI
  • Guerrero C, Lerendegui-Marco J, Paul M, Tessler M, Heinitz S, Domingo-Pardo C, et al.
    Neutron capture on the s-process branching point 171Tm via time-of-flight and activation
    Physical Review Letters. 2020; 125(14): 142701 (8 pp.). https://doi.org/10.1103/PhysRevLett.125.142701
    DORA PSI
  • Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
    Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
    Nuclear Technology. 2020; 206(10): 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
    DORA PSI
  • Hursin M, Pelloni S, Vasiliev A, Ferroukhi H
    Treatment of the implicit effect in Shark-X
    Annals of Nuclear Energy. 2020; 138: 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
    DORA PSI
  • Khvostov G
    Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
    Nuclear Engineering and Technology. 2020; 52(12): 2887-2900. https://doi.org/10.1016/j.net.2020.05.015
    DORA PSI
  • Khvostov G
    Analytical criteria for fuel fragmentation and burst FGR during a LOCA
    Nuclear Engineering and Technology. 2020; 52(10): 2402-2409. https://doi.org/10.1016/j.net.2020.03.009
    DORA PSI
  • Khvostov G
    Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
    Nuclear Engineering and Technology. 2020; 52(1): 135-147. https://doi.org/10.1016/j.net.2019.07.010
    DORA PSI
  • Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D
    Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
    Annals of Nuclear Energy. 2020; 136: 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
    DORA PSI
  • Konarski P, Cozzo C, Khvostov G, Ferroukhi H
    Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
    Kerntechnik. 2020; 85(6): 419-425. https://doi.org/10.3139/124.200072
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Uncertainty propagation based on correlated sampling technique for nuclear data applications
    EPJ Nuclear Sciences and Technologies. 2020; 6: 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
    EPJ Nuclear Sciences and Technologies. 2020; 6: 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
    DORA PSI
  • Mala P, Pautz A
    Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
    Nuclear Engineering and Technology. 2020; 52(11): 2431-2441. https://doi.org/10.1016/j.net.2020.04.022
    DORA PSI
  • Mazzone A, Cristallo S, Aberle O, Alaerts G, Alcayne V, Amaducci S, et al.
    Measurement of the 154Gd(n,γ) cross section and its astrophysical implications
    Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2020; 804: 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
    DORA PSI
  • Mora DF, Costa Garrido O, Mukin R, Niffenegger M
    Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
    Engineering Fracture Mechanics. 2020; 238: 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
    DORA PSI
  • Morató S, Bernal Á, Miró R, Roman JE, Verdú G
    Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
    Annals of Nuclear Energy. 2020; 137: 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Assessment of nTRACER and PARCS performance for VVER configurations
    Nuclear Science and Engineering. 2020; 194(11): 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
    DORA PSI
  • Pelloni S, Rochman D
    Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
    Annals of Nuclear Energy. 2020; 145: 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
    DORA PSI
  • Plompen AJM, Cabellos O, De Saint Jean C, Fleming M, Algora A, Angelone M, et al.
    The joint evaluated fission and fusion nuclear data library, JEFF-3.3
    European Physical Journal A: Hadrons and Nuclei. 2020; 56(7): 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9
    DORA PSI
  • Puragliesi R
    Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
    Nuclear Engineering and Design. 2020; 356: 110365 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110365
    DORA PSI
  • Rochman D, Koning AJ, Sublet J-C
    A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
    Nuclear Data Sheets. 2020; 163: 163-190. https://doi.org/10.1016/j.nds.2019.12.003
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Seidl M, Basualdo J
    Improvement of PIE analysis with a full core simulation: the U1 case
     
    Annals of Nuclear Energy. 2020; 148: 107706 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107706
    DORA PSI
  • Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
    Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
    European Physical Journal Plus. 2020; 135: 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
    DORA PSI
  • Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
    Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
    Annals of Nuclear Energy. 2020; 148: 107727 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107727
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
    Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
    Annals of Nuclear Energy. 2020; 148: 107756 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107756
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    The OFFBEAT multi-dimensional fuel behavior solver
    Nuclear Engineering and Design. 2020; 358: 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
    DORA PSI
  • Siefman D, Hursin M, Perret G, Pautz A
    Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
    Progress in Nuclear Energy. 2020; 121: 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
    DORA PSI
  • Siefman D, Hursin M, Sjostrand H, Schnabel G, Rochman D, Pautz A
    Data assimilation of post-irradiation examination data for fission yields from GEF
    EPJ Nuclear Sciences and Technologies. 2020; 6: 52 (17 pp.). https://doi.org/10.1051/epjn/2020015
    DORA PSI
  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
    Annals of Nuclear Energy. 2020; 135: 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
    DORA PSI
  • Solans V, Rochman D, Ferroukhi H, Vasiliev A, Pautz A
    Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
    Nuclear Engineering and Design. 2020; 370: 110897 (11 pp.). https://doi.org/10.1016/j.nucengdes.2020.110897
    DORA PSI
  • Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
    A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
    Annals of Nuclear Energy. 2020; 144: 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
    DORA PSI
  • Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
    A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
    IEEE Transactions on Nuclear Science. 2020; 67(4): 625-635. https://doi.org/10.1109/TNS.2020.2977530
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 971: 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
    DORA PSI

Seidl M, Schillebeeckx P, Rochman D

On the potential to increase the accuracy of source term calculations for spent nuclear fuel from an industry perspective
atw Int. J. Nucl. Power. 2020:353-361.
DORA PSI

 

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  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Application of causality analysis on nuclear reactor systems
    Chaos: An Interdisciplinary Journal of Nonlinear Science. 2019; 29(4): 043126 (16 pp.). https://doi.org/10.1063/1.5083905
    DORA PSI
  • Clifford I, Pecchia M, Mukin R, Cozzo C, Ferroukhi H, Gorzel A
    Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
    Annals of Nuclear Energy. 2019; 130: 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
    DORA PSI
  • 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
  • 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
  • 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
  • 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
  • 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

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

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

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

 

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Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
N_TOF Collaboration including D. Rochman
EPJ Web of Conferences 178, 03004 (2018)
https://doi.org/10.1051/epjconf/201817803004

Technical note: On modeling central void formation in LWR fuel pellets due to hightemperature restructuring
G. Khvostov
Nuclear Engineering and Design
https://doi.org/10.1016/j.net.2018.07.003
 

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SFCOMPO-2.0: An OECD NEA Database Of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, And Operating Data
F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havlu, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. RantamäKi, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S. Van Winckel, A. Vasiliev, T. Watanabe, Toru Yamamoto, Toshihisa Yamamoto
Annals of Nuclear Energy 110 (2017) 779 788
http://dx.doi.org/10.1016/j.anucene.2017.07.022

Modelling And Analysis Of Selected OECD PKL3 Station-Blackout Experiments Using TRACE
R. Mukin, I. Clifford, O. Zerkak, H. Ferroukhi
Nuclear Engineering and Technology, Net 473. (2017)
https://doi.org/10.1016/j.net.2017.12.005

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Steady-State CFD Simulations Of An Eprtm Reactor Pressure Vessel: A Validation Study Based On The Juliette Experiments
R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Nuclear Engineering And Design, Vol. 300, Pp. 41 56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025

 

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A Dynamic Event Tree Informed Approach To Probabilistic Accident Sequence Modeling: Dynamics And Variabilities In Medium LOCA
D.R. Karanki, T-W. Kim, V.N. Dang
Reliability Engineering And System Safety, Vol. 142, Pp. 78 91 (2015)
http://dx.doi.org/10.1016/j.ress.2015.04.011

Gen-Foam: A Novel Openfoam Based Multi-Physics Solver FOR2d/3d Transient Analysis Of Nuclear Reactors
C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk
Nuclear Engineering And Design, Vol. 294, Pp. 24-37, (2015)

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)

Review Of Multi-Physics Temporal Coupling Methods For Analysis Of Nuclear Reactors
O. Zerkak, T. Kozlowski, I. Gajev
Annals of Nuclear Energy Vol. 84, Pp. 225-233 (2015)

Modelling Guidelines For Core Exit Temperature Simulations With System Codes
J. Freixa V. MartíNez-Quiroga, O. Zerkak, F. ReventóS
Nuclear Engineering and Design, Vol. 286, Pp. 116-129 (2015)

 

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Assessment Of GOTHIC And TRACE Codes Against Selected Panda Experiments On A Passive Containment Condenser
D. Papini, C. Adamsson, M. Andreani, H-M. Prasser
Nuclear Engineering and Design, Vol. 278, Pp. 542-557 (2014)

Post-Test Thermal-Hydraulic Analysis Of Two Intermediate LOCA Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, W-W. Kim, A. Manera
Nuclear Engineering And Design, Vol. 264, Pp 153-160 (2013)
http://dx.doi.org/10.1016/j.nucengdes.2013.02.023

Large Eddy Simulation Of The Differentially Heated Cubic Cavity Flow By The Spectral Element Method
C. Bosshard, A. Dehbi, E. Leriche, R. Puragliesi, A. Soldati
Computers And Fluids, Vol. 86, Pp. 210-227 (2013)

Simulation Of Halden IFA-650 Loss-Of-Coolant Accidents Tests With TRACE
Y. Aounallah
Kerntechnik, Vol 77, Pp 316-323 (2012)

Analysis Of The Isp-50 Direct Vessel Injection Sbloca In The ATLAS Facility Witth The RELAP5/MOD3.3 Code
M. Sharabi, J. Freixa
Nuclear Engineering And Technology, Vol. 44, Pp 709-718 (2012)

Analysis Of Void Fraction Distribution And Departure From Nucleate Boiling In Single Subchannel And Bundle Geometries Using Subchannel, System, And Computational Fluid Dynamics Codes
T-W. Kim, V. Petrov, A. Manera, S. Lo
Science And Technology of Nuclear Installations, Vol.2012, Article Id 746467 (2012)

Quantitative Evaluation Of Change In Core Damage Frequency By Postulated Power Uprate: Medium-Break Loss-Of-Coolant-Accidents
T-W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Annals of Nuclear Energy, Vol. 47, September 2012, Pp. 69-80 (2012)

Remarks On Consistent Development Of Plant Nodalizations: An Example Of Application To The Rosa Integral Test Facility
J. Freixa, A. Manera
Science And Technology of Nuclear Installations, Vol. 2012, Article Id 158617 (2012)

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)

Analysis Of An Ads Spurious Opening Event At A BWR/6 By Means Of The TRACE Code
K. Nikitin, A. Manera
Nuclear Engineering And Design, Doi: 10.1016/J.Nucengdes2011.03.021 (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)

Uncertainty And Sensitivity Analysis Of A LBLOCA In A PWR Nuclear Power Plant: Results Of The Phase V Of The Bemuse Programme
M. Perez, F. Reventosa, L. Batet, A. Guba, I. TóTh, T. Mieusset, P. Bazin, A. De CréCy, S. Borisov, T. Skorek, H. Glaeser, J. Joucla, P. Probst, A. Ui, B.D. Chung, D.Y. Oh, R. Pernica, M. Kyncl, J. Macek, A. Manera, J. Freixa, A. Petruzzi, F. D’Auria, A. Del Nevo
Nuclear Engineering And Design, Vol. 241, Issue 10, Pp 4206-4222, October 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)

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)

Development Of A Wide-Range Pre-Chf Convective Boiling Correlation
Y. Aounallah
Journal of Nuclear Science And Technology, Vol. 47(4), Pp. 357-366, 2010

Analysis Of An Rpv Upper Head SBLOCA oca At The Rosa Facility Using TRACE
J. Freixa, A. Manera
Nuclear Engineering And Design, Available Online 30 March, 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 LBLCOA 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)

Investigating The ESBWR Stability With Experimental And Numerical Tools: A Comparative Study
M. Rohde, C. Marcel, Manera. P, Van. A, Hagen. Der, H. T, J. J, B. Shiralkar
Nuclear Engineering and Des. (Issn 0029-5493), 240(2), 375-384 (2010)

 

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Single-Phase Mixing Studies By Means Of A Directly Coupled CFD/System-Code Tool
D. Bertolloto, A. Manera, S. Frey, H-M. Prasser, R. Chawla
Annals of Nuclear Energy, Volume 36, Issue 3, Pp 310-316 , April 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)

Comparison Between Wire-Mesh Sensors And Conductive Needle-Probes For Measurements Of Two-Phase Flow Parameters
A. Manera, B. Ozar, S. Paranjape, M. Ishii, H. Prasser,
Nuclear Engineering and Des. (Issn 0029-5493), 239(9), 1718-1724 (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)

A Separate-Effect-Based New Appraisal Of Convective Boiling And Its Suppression
Y. Aounallah
Journal of Nuclear Sci. And Techn. (Issn 0022-3131), 45(2), 149-159 (2008)

One- And Two-Dimensional Standing Pressure Waves And One-Dimensional Travelling Pulses Using The US-NRC Nuclear Systems Analysis Code TRACE
W. Barten, A. Manera A., R. Macian-Juan
Nuclear Engineering and Des. (Issn 0029-5493), 238, 2568-2582 (2008)

Analysis Of The Capability Of System Codes To Model Cavitation Water Hammers: Simulation Of Umsicht Water Hammer Experiments With TRACE And RELAP5
W. Barten, A. Jasiulevicius, A. Manera, R. Macian-Juan, O. Zerkak
Nuclear Engineering and Des. (Issn 0029-5493), 238, 1129-1145 (2008)

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)

A Statistical Methodology For Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, R. Macian-Juan, R. Chawla
Annals of Nuclear Energy, 34 (8), 628-640 (2007)

Analysis Of The Leibstadt Power Plant Condensate And Feedwater Systems During Selected Operational Transients
O. Zerkak, P. Coddington
Nuclear Science And Engineering, 237(11), 1195-1208 (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)

 

Investigations On The Stability Of The Flow Characteristics In A Bubble Column
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Chem. Engineering and Technol. (Issn 1521-4125), 9, 1066-1072 (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)

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)

 

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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)

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 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)

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

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.

 

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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)

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
 

 

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General Contact

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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