LRT Publication List (since 2018)

  • Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
    Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
    Annals of Nuclear Energy. 2020; 139: 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
    DORA PSI
  • Andreani M, Kapulla R, Kelm S, Paladino D, Paranjape S
    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
    Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021110 (18 pp.). https://doi.org/10.1115/1.4046296
    DORA PSI
  • Bernal A, Pecchia M, Rochman D, Vasiliev A, Ferroukhi H
    Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1197 (8 pp.).
    DORA PSI
  • Betschart T, Lind T, Prasser H-M
    Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
    Nuclear Engineering and Design. 2020; 366: 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
    DORA PSI
  • Chionis D, Dokhane A, Belblidia L, Ferroukhi H, Girardin G, Pautz A
    Development and verification of a methodology for neutron noise response to fuel assembly vibrations
    Annals of Nuclear Energy. 2020; 147: 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
    DORA PSI
  • Hombourger B, Křepel J, Pautz A
    The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
    Annals of Nuclear Energy. 2020; 144: 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
    DORA PSI
  • Hursin M, Rochman D, Vasiliev A, Ferroukhi H, Pautz A
    Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1172 (10 pp.).
    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. 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
  • Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
    Validation of axial void profile measured by neutron noise techniques in CROCUS
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1173 (8 pp.).
    DORA PSI
  • Kalilainen J, Nichenko S, Krepel J
    Evaporation of materials from the molten salt reactor fuel under elevated temperatures
    Journal of Nuclear Materials. 2020; 533: 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
    DORA PSI
  • Khvostov G
    Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
    Nuclear Engineering and Technology. 2020. 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
  • Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Polhus J, et al.
    Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1573 (9 pp.).
    DORA PSI
  • Lind T, Campbell S, Herranz LE, Kissane M, Song JH
    A summary of fission-product-transport phenomena during SGTR severe accidents
    Nuclear Engineering and Design. 2020; 363: 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
    DORA PSI
  • Mala P, Pautz A
    Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
    Nuclear Engineering and Technology. 2020. https://doi.org/10.1016/j.net.2020.04.022
    DORA PSI
  • Mala P, Pautz A, Ferroukhi H, Vasiliev A
    Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1583 (8 pp.).
    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
  • Mylonakis AG, Demazière C, Vinai P, Lamirand V, Rais A, Pakari O, et al.
    CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1207 (9 pp.).
    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. https://doi.org/10.1080/00295639.2020.1753418
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1285 (8 pp.).
    DORA PSI
  • Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyama Y, Gauntt R, et al.
    Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
    Nuclear Technology. 2020. https://doi.org/10.1080/00295450.2020.1724731
    DORA PSI
  • Pelloni S, Rochman D
    Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
    Annals of Nuclear Energy. 2020; 145: 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
    DORA PSI
  • Perret G, Rochman D, Vasiliev A, Ferroukhi H
    Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1174 (10 pp.).
    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
    The European Physical Journal A. 2020; 56(7): 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9
    DORA PSI
  • Pázsit I, Hursin M, Nylén H, Dykin V
    Reconstructing the axial void velocity profile in BWRs from measurements of the in-core neutron noise
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1337 (8 pp.).
    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
  • 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
  • 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
  • Soubelet B, Adams R, Kromer H, Prasser H-M
    Calibration technique and sample measurement database for material decomposition imaging using a compact deuterium-deuterium (D-D) fast neutron generator
    Radiation Physics and Chemistry. 2020; 176: 108930 (18 pp.). https://doi.org/10.1016/j.radphyschem.2020.108930
    DORA PSI
  • Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
    A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
    Annals of Nuclear Energy. 2020; 144: 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
    DORA PSI
  • Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
    Enhancement of validation studies for reactor dosimetry and ativation predictions with the nuclear data sampling methodology
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1427 (8 pp.).
    DORA PSI
  • Verma V, Chionis D, Dokhane A, Ferroukhi H
    Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
    In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1270 (8 pp.).
    DORA PSI
  • Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
    A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
    IEEE Transactions on Nuclear Science. 2020; 67(4): 625-635. https://doi.org/10.1109/TNS.2020.2977530
    DORA PSI
  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    Statistical burnup distribution of moving pebbles in the HTR-PM reactor
    Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021108 (14 pp.). https://doi.org/10.1115/1.4044910
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 971: 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
    DORA PSI
  • Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
    Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility
    In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:117-122. https://doi.org/10.1007/978-3-030-22204-8_4
    DORA PSI
  • Andreani M, Paranjape S
    Modelling of the interaction of two heat sources simulating the thermal effects of PARs
    Presented at: ICAPP 2019 - International congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Andreani M, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, Herranz LE, et al.
    Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
    Nuclear Engineering and Design. 2019; 354: 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
    DORA PSI
  • Babiano-Suarez V, Caballero L, Domingo-Pardo C, Ladarescu I, Aberle O, Alcayne V, et al.
    Characterization and first test of an i-TED prototype at CERN n_TOF
    In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:169-173. https://doi.org/10.1007/978-3-030-22204-8_18
    DORA PSI
  • Barbagallo M, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Bécares V, et al.
    (n,cp) reactions study at the n_TOF facility at CERN: results for the cosmological lithium problem
    In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:259-264.
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Application of causality analysis on nuclear reactor systems
    Chaos: An Interdisciplinary Journal of Nonlinear Science. 2019; 29(4): 043126 (16 pp.). https://doi.org/10.1063/1.5083905
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). LaGrange Park, USA: American Nuclear Society (ANS); 2019:1960-1969.
    DORA PSI
  • Clifford I, Cozzo C, Ferroukhi H
    First assessments of the dynamic gap conductance model in TRACE
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:4624-4636.
    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
  • Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
    Modeling of the U3Si2/SiC fuel system behavior for a RIA scenario
    In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
    DORA PSI
  • Dehbi A, Kelm S, Kalilainen J, Mueller H
    The influence of thermal radiation on the free convection inside enclosures
    Nuclear Engineering and Design. 2019; 341: 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
    DORA PSI
  • Fernandez Moguel L, Lind T, Rýdl A
    Analysis of fission product transport in unit 3 of Fukushima Daiichi
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:508-521.
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Lind T
    Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
    Annals of Nuclear Energy. 2019; 130: 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Lind T
    Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
    Annals of Nuclear Energy. 2019; 123: 59-77. https://doi.org/10.1016/j.anucene.2018.09.008
    DORA PSI
  • Gallego-Marcos I, Kudinov P, Villanueva W, Kapulla R, Paranjape S, Paladino D, et al.
    Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments
    Nuclear Engineering and Design. 2019; 347: 67-85. https://doi.org/10.1016/j.nucengdes.2019.03.011
    DORA PSI
  • Griffin PJ, Koning AJ, Rochman D
    Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
    IEEE Transactions on Nuclear Science. 2019; 66(7): 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
    DORA PSI
  • Hennig D, Lange C, Rizwan-uddin, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
    Progress in Nuclear Energy. 2019; 115: 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
    DORA PSI
  • Hennig D, Rizwan-uddin, Lange C, Dokhane A, Knospe A
    Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
    Progress in Nuclear Energy. 2019; 113: 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
    DORA PSI
  • Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1107-1118.
    DORA PSI
  • Hombourger B, Křepel J, Pautz A
    Breed-and-burn fuel cycle in molten salt reactors
    EPJ Nuclear Sciences and Technologies. 2019; 5: 15 (10 pp.). https://doi.org/10.1051/epjn/2019026
    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 by neutron noise technique
    Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
    DORA PSI
  • Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
    Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
    Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
    DORA PSI
  • Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
    Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:024 (14 pp.).
    DORA PSI
  • Kalilainen J, Lind T, Stuckert J, Stegmaier U
    Aerosol results of the QUENCH-18 bundle test
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:019 (11 pp.).
    DORA PSI
  • Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
    The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
    Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
    DORA PSI
  • Kapulla R, Paranjape S, Falsetti C, Paladino D
    High spatial resolution PIV measurements in the PANDA facility
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    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
  • Lamirand V, Laureau A, Rochman D, Perret G, Gruel A, Leconte P, et al.
    An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
    DORA PSI
  • Laureau A, Lamirand V, Rochman D, Pautz A
    Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
    In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
    DORA PSI
  • Lind T, Campbell S, Herranz LE, Kissane M, Song JH
    A summary of fission-product-transport phenomena during SGTR severe accidents
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:4063-4075.
    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
  • Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
    Overwiew and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 3
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1133-1146.
    DORA PSI
  • Mala P, Pautz A, Ferroukhi H
    EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:1640-1649.
    DORA PSI
  • Manara D, Jacquemain D, Van Dorsselaere JP, Bottomley PD, Adorni M, Journeau C, et al.
    Severe accident research priority ranking: a new assessment eight years after the Fukushima Daiichi accident
    In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:1-25.
    DORA PSI
  • Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
    Data for the s process from n_TOF
    In: Formicola A, Junker M, Gialanella L, Imbriani G, eds. Nuclei in the cosmos XV. Vol. 219. Springer proceedings in physics. Cham: Springer; 2019:63-70. https://doi.org/10.1007/978-3-030-13876-9_11
    DORA PSI
  • Mora DF, Mukin R, Costa Garrido O, Niffenegger M
    Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
    In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
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    BWR-4 ATWS modeling with RELAP5-S3K
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    PMSYS: plant management system as a part of Swiss Simulation Platform
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     Assessment of nTRACER and parcs performance for VVER configurations
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    Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
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    Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
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    Gas redistribution caused by interacting sources in the presence of a vertical condenser
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
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    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
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  • Pecchia M, Vasiliev A, Perret G, Ferroukhi H
    Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments
    Presented at: ICNC 2019 - 11th international conference on nuclear criticality safety; September 15-20, 2019; Paris, France.
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    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
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    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
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    Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
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    Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
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    Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
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    Towards the validation of neutron noise simulators: qualification of data acquisition systems
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    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
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    Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
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    Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
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    Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
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    Data assimilation of post irradiation examination experiments to adjust fission yields
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    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for unit 2
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    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
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    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
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    Nuclear astrophysics at n_TOF facility, CERN
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    Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
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    Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
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    Materials. 2019; 12(3): 494 (30 pp.). https://doi.org/10.3390/ma12030494
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    Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
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    Presented at: ANS annual meeting 2019. The value of nuclear; June 9-13, 2019; Minneapolis, USA.
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    Study of level swell for a Filtered Containment Venting System at the VEFITA facility
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    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
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    Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
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    In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:302-309.
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    Experimental studies on retention of iodine in a wet scrubber
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    Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
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    ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data
    Nuclear Data Sheets. 2018; 148: 1-142. https://doi.org/10.1016/j.nds.2018.02.001
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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)
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  • Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
    PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1001-1012.
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    On the characteristics of the flow and heat transfer in the core bypass region of a PWR
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    Annals of Nuclear Energy. 2018; 120: 880-887. https://doi.org/10.1016/j.anucene.2018.06.043
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    SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
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    Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
    In: Proceedings of the PHYTRA4 conference. sine loco: American Nuclear Society (ANS); 2018:91-102.
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    Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
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    Mid wave infrared thermography of water films in condensing and evaporating environments
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    Improving activation cross sections for fusion applications
    Fusion Science and Technology. 2018; 73(1): 13-24. https://doi.org/10.1080/15361055.2017.1372682
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    The role of nuclear data for fusion nuclear technology
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    Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments
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  • Gouëllo M, Kalilainen J, Kärkelä T, Auvinen A
    Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
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    Importance of treating correlations in the uncertainty quantification of radiation damage metrics
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  • Hombourger B, Krepel J, Mikityuk K, Pautz A
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    Determination of sobol sensitivity indices for correlated inputs with SHARK-X
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    Testing of a sCVD diamond detection system in the CROCUS reactor
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  • Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A
    Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
    Annals of Nuclear Energy. 2018; 111: 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
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    Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions
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    Aerosol depletion in natural circulation in simplified geometry
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    Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
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    Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
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    Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
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    Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
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    Comparison of fast reactors performance in the closed U-Pu and Th-U cycle
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    Improvement of a compact fast neutron generator for imaging applications
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    Design of separated element reflector experiments in CROCUS: PETALE
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    Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
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  • Mukin R, Clifford I, Zerkak O, Ferroukhi H
    Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
    Nuclear Engineering and Technology. 2018; 50(3): 356-367. https://doi.org/10.1016/j.net.2017.12.005
    DORA PSI
  • Mukin R, Clifford I, Ferroukhi H, Niffenegger M
    Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81749 (7 pp.). https://doi.org/10.1115/ICONE26-81749
    DORA PSI
  • Mukin R, Seidl M, Clifford I, Ferroukhi H
    Sensitivity of CTF solution to subchannel window size
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82546 (11 pp.). https://doi.org/10.1115/ICONE26-82546
    DORA PSI
  • Mukin R, Puragliesi R, Pecchia M, Seidl M
    Subchannel modeling of single rod bowing in a bundle geometry
    Nuclear Engineering and Design. 2018; 340: 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
    DORA PSI
  • Ngayam-Happy R, Cozzo C, Khvostov G, Krack M, Ferroukhi H
    Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
    Presented at: ANS Best estimate plus uncertainty International conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Noguere G, Tommasi J, Privas E, Schmidt K-H, Rochman D
    Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu
    European Physical Journal Plus. 2018; 133(3): 99 (14 pp.). https://doi.org/10.1140/epjp/i2018-11926-y
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Braun L, Frajtag P, Pautz A
    Current mode neutron noise measurements in the zero power reactor CROCUS
    In: Lyoussi A, Carette M, Giot M, Le Dû P, Reynard-Carette C, Schyns M, et al., eds. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 170. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2018:04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Godat D, Hursin M, Frajtag P, et al.
    Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Frajtag P, Pautz A
    Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
    IEEE Transactions on Nuclear Science. 2018; 65(9): 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
    DORA PSI
  • Papadionysiou M, Perret G, Zboray R, Adams R, Mosset J-B
    Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
    Nuclear Engineering and Design. 2018; 332: 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
    DORA PSI
  • Papadopoulos P, Lind T, Prasser H-M
    Analyzing droplet size distributions inside a self-priming venturi scrubber for filtered containment venting systems
    In: Proceedings of the 2018 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82227 (7 pp.). https://doi.org/10.1115/ICONE26-82227
    DORA PSI
  • Paviet P, Alekseev P, Fazio C, Fratoni M, Hwang I, Kelly J, et al.
    GEN IV education and training initiative via public webinars
    In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Vienna: International Atomic Energy Agency; 2018:009 (8 pp.).
    DORA PSI
  • Pelloni S, Rochman D
    Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
    Annals of Nuclear Energy. 2018; 115: 323-342. https://doi.org/10.1016/j.anucene.2018.01.037
    DORA PSI
  • Pelloni S, Panadero A-L, Mikityuk K, Pautz A
    Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties
    In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:050 (10 pp.).
    DORA PSI
  • Pelloni S, Rochman D
    Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
    Annals of Nuclear Energy. 2018; 121: 361-373. https://doi.org/10.1016/j.anucene.2018.07.043
    DORA PSI
  • Perret G, Rahman S, Wicaksono D
    Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Prasser H-M, Janasz F, Suckow D, Szogradi M
    Non-condensable gas plugging and mixing behavior in PWR steam generator tubes during reflux condensation
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82350 (10 pp.). https://doi.org/10.1115/ICONE26-82350
    DORA PSI
  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
    DORA PSI
  • Rahman S, Karanki DR, Epiney A, Wicaksono D, Zerkak O, Dang VN
    Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis
    Reliability Engineering and System Safety. 2018; 175: 62-78. https://doi.org/10.1016/j.ress.2018.03.009
    DORA PSI
  • Rimpault G, Buiron L, Stauff NE, Kim TK, Taiwo TA, Lee Y-K, et al.
    Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
    In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:220 (13 pp.).
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
    Best estimate plus uncertainty analysis for the 244CM prediction in spent fuel characterization
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
    Consistent criticality and radiation studies of Swiss spent nuclear fuel: the CS2M approach
    Journal of Hazardous Materials. 2018; 357: 384-392. https://doi.org/10.1016/j.jhazmat.2018.05.041
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Dokhane H, Koning A
    How inelastic scattering stimulates nonlinear reactor core parameter behaviour
    Annals of Nuclear Energy. 2018; 112: 236-244. https://doi.org/10.1016/j.anucene.2017.10.018
    DORA PSI
  • Rochman D, Bauge E, Vasiliev A, Ferroukhi H, Pelloni S, Koning AJ, et al.
    Monte Carlo nuclear data adjustment via integral information
    European Physical Journal Plus. 2018; 133(12): 537. https://doi.org/10.1140/epjp/i2018-12361-x
    DORA PSI
  • Rochman DA, Bauge E, Vasiliev A, Ferroukhi H, Perret G
    Nuclear data correlation between different isotopes via integral information
    EPJ Nuclear Sciences and Technologies. 2018; 4: 7 (10 pp.). https://doi.org/10.1051/epjn/2018006
    DORA PSI
  • Rochman DA, Vasiliev A, Dokhane A, Ferroukhi H
    Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
    EPJ Nuclear Sciences and Technologies. 2018; 4: 6 (15 pp.). https://doi.org/10.1051/epjn/2018005
    DORA PSI
  • Rýdl A, Fernandez-Moguel L, Lind T
    Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
    Nuclear Technology. 2018; 205(5): 655-670. https://doi.org/10.1080/00295450.2018.1511213
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381
    DORA PSI
  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(10 pp.).
    DORA PSI
  • Siefman D, Hursin M, Rochman D, Pelloni S, Pautz A
    Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
    European Physical Journal Plus. 2018; 133(10): 429 (10 pp.). https://doi.org/10.1140/epjp/i2018-12303-8
    DORA PSI
  • Simakov SP, Fischer U, Koning AJ, Konobeyev AY, Rochman DA
    Iron NRT- and arc-displacement cross sections and their covariances
    Nuclear Materials and Energy. 2018; 15: 244-248. https://doi.org/10.1016/j.nme.2018.05.006
    DORA PSI
  • Sjöstrand H, Asquith N, Helgesson P, Rochman D, van der Marck S
    Efficient use of Monte Carlo: the fast correlation coefficient
    EPJ Nuclear Sciences and Technologies. 2018; 4: 15 (5 pp.). https://doi.org/10.1051/epjn/2018019
    DORA PSI
  • Sublet J-C, Koning A, Rochman D
    TENDL-2017: the making of multi-faceted technological nuclear data library
    In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(7 pp.).
    DORA PSI
  • Tambouratzis T, Chionis D, Dokhane A
    General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
    In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:524-531. https://doi.org/10.1109/SSCI.2018.8628700
    DORA PSI
  • Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
    On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel
    Annals of Nuclear Energy. 2018; 116: 57-68. https://doi.org/10.1016/j.anucene.2018.01.046
    DORA PSI
  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    Statistical burnup distribution of moving pebbles in HTR-PM reactor
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082
    DORA PSI
  • Zboray R, Bolesch C, Prasser H-M
    Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
    Nuclear Engineering and Design. 2018; 336: 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
    DORA PSI

Contact

Research Division
Nuclear Energy and Safety
Paul Scherrer Institute
OHSA/E72
5232 Villigen PSI
Switzerland

Division Head
Prof. Dr. Andreas Pautz
Telephone: +41 56 310 3497
E-mail: Andreas.Pautz@psi.ch

Executive Assistant
Ute D. Mayer
Telephone: +41 56 310 2740
E-mail: Ute.Mayer@psi.ch
Ramona Dreier
Telephone: +41 56 310 2741
E-mail: Ramona.Dreier@psi.ch

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

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