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
  • 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, 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
  • 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
    Analytical criteria for fuel fragmentation and burst FGR during a LOCA
    Nuclear Engineering and Technology. 2020. 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
  • 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
  • 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
  • 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
  • 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
  • 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, 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
  • 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, 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
  • 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, 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. 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. https://doi.org/10.1007/978-3-030-22204-8_18
    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.
    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 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019.
    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). La Grange Park: 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). La Grange Park: American Nuclear Society (ANS); 2019.
    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.
    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.
    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. 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. 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 2019). La Grange Park, IL, USA: 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). La Grange Park: American Nuclear Society (ANS); 2019.
    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.
    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.
    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. 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: ASME 2019 pressure vessels & piping conference. Conference proceedings. Materials and fabrication. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019. https://doi.org/10.1115/PVP2019-94019
    DORA PSI
  • Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
    Screening analysis for pressurized thermal shock (PTS) transient scenarios
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019.
    DORA PSI
  • Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
    Uncertainties in pressurized thermal shock analyses
    In: ASME 2019 pressure vessels & piping conference. Conference proceedings. Design and analysis. Vol. 3. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019. https://doi.org/10.1115/PVP2019-94076
    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
  • Nikitin K, Clifford I, Ferroukhi H
    PMSYS: plant management system as a part of Swiss Simulation Platform
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). LaGrange Park, USA: American Nuclear Society (ANS); 2019.
    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
    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.
    DORA PSI
  • Papadopoulos P, Tietze S, Suckow D, Ceder SJ, Roth B, Lind T
    Hydrodynamic characterisation inside a wet scrubber for different flow regimes relevant for pool scrubbing and FCVS
    In: Proceedings of the ERMSAR 2019. Prague: AF POWER agency; 2019.
    DORA PSI
  • Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
    Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
    Nuclear Technology. 2019; 205(1-2): 153-173. https://doi.org/10.1080/00295450.2018.1505356
    DORA PSI
  • Paranjape S, Mignot G, Kapulla R, Paladino D
    Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
    Nuclear Engineering and Design. 2019; 342: 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017
    DORA PSI
  • 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, France.
    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, 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.
    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). La Grange Park: 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; 205(12): 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
    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. 2019. https://doi.org/10.1016/j.nucengdes.2019.110365
    DORA PSI
  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019.
    DORA PSI
  • Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
    Towards the validation of neutron noise simulators: qualification of data acquisition systems
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019.
    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
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
    In: Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019.
    DORA PSI
  • Scolaro A, Robert Y, Fiorina C, Clifford I, Pautz A
    Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
    In: Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019.
    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). La Grange Park: 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
  • Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
    Fission program at n_TOF
    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. https://doi.org/10.1051/epjconf/201921103006
    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
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    Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
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    Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
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    Analyzing droplet size distributions inside a self-priming venturi scrubber for filtered containment venting systems
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    Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
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    Non-condensable gas plugging and mixing behavior in PWR steam generator tubes during reflux condensation
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    Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
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    Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
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    First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
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    Nuclear Materials and Energy. 2018; 15: 244-248. https://doi.org/10.1016/j.nme.2018.05.006
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  • 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.
    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. 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. 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

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

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