LRT Publication List (since 2018)

  • 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
  • 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
  • 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 2019). Illinois: American Nuclear Society (ANS); 2019.
    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 2019). Illinois: American Nuclear Society (ANS); 2019.
    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
  • Jaeckel B, 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. ; 2019.
    DORA PSI
  • Kalilainen J, Lind T, Stuckert J, Stegmaier U
    Aerosol results of the QUENCH-18 bundle test
    In: Proceedings of the ERMSAR 2019. ; 2019.
    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. https://www.sfen-icapp2019.org/.
    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. 2019. https://doi.org/10.1016/j.net.2019.07.010
    DORA PSI
  • Koning AJ, Rochman D, Sublet J-C, Dzysiuk N, Fleming M, van der Marck S
    TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology
    Nuclear Data Sheets. 2019; 155: 1-55. https://doi.org/10.1016/j.nds.2019.01.002
    DORA PSI
  • Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
    Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
    Applied Radiation and Isotopes. 2019; 145: 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
    DORA PSI
  • Lind T, 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 2019). Illinois: American Nuclear Society (ANS); 2019.
    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 2019). Illinois: American Nuclear Society (ANS); 2019.
    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. ; 2019.
    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
  • Paranjape S, Mignot G, Kapulla R, Paladino D
    Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
    Nuclear Engineering and Design. 2019; 342: 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    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. https://www.sfen-icapp2019.org/.
    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
  • Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyana Y, Gaunt R, et al.
    Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). Illinois: American Nuclear Society (ANS); 2019.
    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. https://doi.org/10.1080/00295450.2019.1591154
    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
  • Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
    Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for unit 2
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). Illinois: American Nuclear Society (ANS); 2019.
    DORA PSI
  • Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
    Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
    Radiation Physics and Chemistry. 2019; 156: 292-299. https://doi.org/10.1016/j.radphyschem.2018.11.017
    DORA PSI
  • Sublet J-C, Bondarenko IP, Bonny G, Conlin JL, Gilbert MR, Greenwood LR, et al.
    Neutron-induced damage simulations: beyond defect production cross-section, displacement per atom and iron-based metrics
    European Physical Journal Plus. 2019; 134(7): 350 (50 pp.). https://doi.org/10.1140/epjp/i2019-12758-y
    DORA PSI
  • Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
    Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
    Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
    DORA PSI
  • Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
    Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
    Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
    DORA PSI
  • Vasiliev A, Herrero J, Pecchia M, Rochman D, Ferroukhi H, Caruso S
    Preliminary assessment of criticality safety constraints for swiss spent nuclear fuel loading in disposal canisters
    Materials. 2019; 12(3): 494. https://doi.org/10.3390/ma12030494
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
    Presented at: ANS Annual meeting 2019. The value of nuclear; June 9-13, 2019; Minneapolis, MN, USA.
    DORA PSI
  • Yang J, Suckow D, Lind T, Prasser H-M
    Study of level swell for a Filtered Containment Venting System at the VEFITA facility
    Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
    DORA PSI
  • Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
    Main results of the European PASSAM project on severe accident source term mitigation
    Annals of Nuclear Energy. 2018; 116: 42-56. https://doi.org/10.1016/j.anucene.2018.02.024
    DORA PSI
  • Andreani M, Paladino D, Papini D
    Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
    Nuclear Engineering and Design. 2018; 339: 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
    DORA PSI
  • Beghi I, Lind T, Prasser H-M
    Experimental studies on retention of iodine in a wet scrubber
    Nuclear Engineering and Design. 2018; 326: 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
    DORA PSI
  • Bousbia Salah A, Ceuca SC, Puragliesi R, Mukin R, Grahn A, Kliem S, et al.
    Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes
    Nuclear Technology. 2018; 203(3): 293-314. https://doi.org/10.1080/00295450.2018.1461517
    DORA PSI
  • Brown DA, Chadwick MB, Capote R, Kahler AC, Trkov A, Herman MW, et al.
    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
    DORA PSI
  • Casanovas A, Domingo-Pardo C, Guerrero C, Lerendegui-Marco J, Calviño F, Tarifeño-Saldivia A, et al.
    Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
    In: Sun Y, ed. 16th international symposium on capture gamma-ray spectroscopy and related topics (CGS16). Vol. 178. EPJ web of conferences. sine loco: EDP Sciences; 2018. https://doi.org/10.1051/epjconf/201817803004
    DORA PSI
  • Clifford I, Pecchia M, Puragliesi R, Vasiliev A, Ferroukhi H
    On the characteristics of the flow and heat transfer in the core bypass region of a PWR
    Nuclear Engineering and Design. 2018; 330: 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
    DORA PSI
  • Cozzo C, Rahman S
    SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
    Progress in Nuclear Energy. 2018; 106: 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
    DORA PSI
  • Di Filippo M, Krepel J, Mikityuk K, Prasser H-M
    Analysis of major group structures used for nuclear reactor simulations
    In: Proceedings of the 26th international conference on nuclear engineering. Vol. 9. ASME; 2018. https://doi.org/10.1115/ICONE26-81445
    DORA PSI
  • Dokhane A, Grandi G, Vasiliev A, Rochman D, Ferroukhi H
    Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
    Annals of Nuclear Energy. 2018; 118: 178-184. https://doi.org/10.1016/j.anucene.2018.04.022
    DORA PSI
  • Dupont J, Mignot G, Paladino D, Prasser H-M
    Mid wave infrared thermography of water films in condensing and evaporating environments
    Nuclear Engineering and Design. 2018; 336: 80-89. https://doi.org/10.1016/j.nucengdes.2017.06.027
    DORA PSI
  • Dzysiuk N, Koning AJ, Rochman D, Fischer U
    Improving activation cross sections for fusion applications
    Fusion Science and Technology. 2018; 73(1): 13-24. https://doi.org/10.1080/15361055.2017.1372682
    DORA PSI
  • 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
    Nuclear Materials and Energy. 2018; 17: 259-268. https://doi.org/10.1016/j.nme.2018.11.011
    DORA PSI
  • Hursin M, Weiss C, Frajtag P, Lamirand V, Perret G, Kavrigin P, et al.
    Testing of a sCVD diamond detection system in the CROCUS reactor
    The European Physical Journal A. 2018; 54(5): 82. https://doi.org/10.1140/epja/i2018-12519-1
    DORA PSI
  • 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
    DORA PSI
  • Kapulla R, Mignot G, Andreani M, Paladino D
    Large Scale Experiments Representing a Containment Natural Circulation Loop during an Accident Scenario
    Science and Technology of Nuclear Installations. 2018: 8989070. https://doi.org/10.1155/2018/8989070
    DORA PSI
  • Kapulla R, Uong D, Zimmer C, Paladino D
    PIV measurements in the vicinity of a steam sparger in the PANDA facility
    Nuclear Engineering and Design. 2018; 336: 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
    DORA PSI
  • Khvostov G
    Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
    Nuclear Engineering and Technology. 2018; 50(7): 1190-1197. https://doi.org/10.1016/j.net.2018.07.003
    DORA PSI
  • Khvostov G
    Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
    Nuclear Engineering and Design. 2018; 328: 36-57. https://doi.org/10.1016/j.nucengdes.2017.12.028
    DORA PSI
  • Kim H, Dehbi A, Kalilainen J
    Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
    Atmospheric Environment. 2018; 186: 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037
    DORA PSI
  • Mignot G, Dupont J, Paranjape S, Ouldrebai H, Bissels W-M, Paladino D, et al.
    Measurement of liquid films thickness in a condensing and re-evaporating environment using attenuation of near infrared light
    Nuclear Engineering and Design. 2018; 336: 64-73. https://doi.org/10.1016/j.nucengdes.2017.06.023
    DORA PSI
  • 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, 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: BEPU 2018: best estimate plus uncertainty international conference. Mult-physics multi-scale simulations with uncertainty; 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
  • 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
  • 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, 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
  • 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
  • Rochman DA
    Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
    EPJ Nuclear Sciences and Technologies. 2018; 4: 35. https://doi.org/10.1051/epjn/2018011
    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
  • Rýdl A, Fernandez-Moguel L, Lind T
    Modeling of Aerosol Fission Product Scrubbing in Experiments and in Integral Severe Accident Scenarios
    Nuclear Technology. 2018. https://doi.org/10.1080/00295450.2018.1511213
    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
  • Vasiliev A, Ferroukhi H, Perret G
    Nuclear data correlation between different isotopes via integral information
    EPJ Nuclear Sciences and Technologies. 2018; 4: 7. https://doi.org/10.1051/epjn/2018006
    DORA PSI
  • 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. https://doi.org/10.1051/epjn/2018005
    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. Vol. 9. ASME; 2018. https://doi.org/10.1115/ICONE26-81082
    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

Secretary
Laura Wenger
Telephone: +41 56 310 2740
E-mail: Laura.Wenger@psi.ch
Ramona Dreier
Telephone: +41 56 310 2741
E-mail: Ramona.Dreier@psi.ch

NES Open positions

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

Directions to PSI

How to get to the Paul Scherrer Institute (description and map)