LRT Publication List 2018 ‒ 2014

2018

  • Analysis of Major Group Structures Used for Nuclear Reactor Simulations Di Filippo M, Krepel J, Mikityuk K, Prasser H
    International Conference on Nuclear Engineering, Proceedings -, - (2018).
    DOI: 10.1115/ICONE26-81445
  • Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code Jo Yunki, Hursin Mathieu, Lee Deokjung, Ferroukhi Hakim, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 111, 141-151 (2018).
    DOI: 10.1016/j.anucene.2017.08.061
  • Cross-observables and cross-isotopes correlations in nuclear data from integral constraints Bauge E, Rochman DA
    EPJ Nuclear Sciences & Technologies 4, 35 (2018).
    DOI: 10.1051/epjn/2018011
  • Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology Pelloni S, Rochman D
    ANNALS OF NUCLEAR ENERGY 342, 323 (2018).
    DOI: 10.1016/j.anucene.2018.01.037
  • ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library Brown DA, Chadwick M B, Capote R, Kahler A C, Trkov A, Herman M W, Sonzogni A A, Danon Y, Carlson A D, Dunn M, Smith D L, Hale G M, Arbanas G, Arcilla R, Bates CR, B Beck, B Becker B, Brown F, Casperson R J, Conlin J, Cullen D E, Descalle M-A, Firestone R, Gaines T, Guber K H, Hawari AI, Holmes J, Johnson T D, Kawano T, Kiedrowski B C, Koning A J, Kopecky S, Leal L, Lestone JP, Lubitz C, M´arquez Dami´an J I, Mattoon C M, McCutchan E A, Mughabghab S, Navratil P, Neudecker D, Nobre GP A, Noguere G, Paris M, Pigni M T, Plompen A J, Pritychenko B, Pronyaev V G, Roubtsov D, Rochman D, Romano P, Schillebeeckx P, Simakov S, Sin M, Sirakov I, Sleaford B, Sobes V, Soukhovitskii E S, Stetcu I, Talou P, Thompson I, van der Marck S, Welser-Sherrill L, Wiarda D, White M, Wormald J L, Wright R Q, Zerkle M, Zerovnik G, Zhu Y
    NUCLEAR DATA SHEETS 142, 1 (2018).
    DOI: 10.1016/j.nds.2018.02.001
  • Efficient use of Monte Carlo: the fast correlation coefficient Sjöstrand H, Asquith N, Helgesson P, Rochman D, Marck S
    EPJ Nuclear Sciences & Technologies 4, 15 (2018).
    DOI: 10.1051/epjn/2018019
  • Iron NRT- and arc-displacement cross sections and their covariances Simakov SP, Fischer U, Koning AJ, Konobeyev AY, Rochman DA
    Nuclear Materials and Energy 15, 244 (2018).
    DOI: 10.1016/j.nme.2018.05.006
  • Large Scale Experiments Representing a Containment Natural Circulation Loop during an Accident Scenario Kapulla R, Mignot G, Paranjape S, Andreani M, Paladino D
    Science and Technology of Nuclear Installations 2018, 1 (2018).
    DOI: 10.1155/2018/8989070
  • Magnetism and the phase diagram of MnSb2O6 Koo C, Werner J, Tzschoppe M, Abdel-Hafiez M, Biswas PK, Sarkar R, Klauss HH, Raganyan GV, Ovchenkov EA, Nikulin AYu, Vasiliev AN, Zvereva EA, Klingeler R
    PHYSICAL REVIEW B 97, 224416 (2018).
    DOI: 10.1103/PhysRevB.97.224416
  • Modelling and Analysis of selected OECD PKL3 Station-Blackout Experiments using TRACE Mukin R, Clifford I, Zerkak O, Ferroukhi H
    Nuclear Engineering and Technology 1, 1-25 (2018).
    DOI: 10.1016/j.net.2017.12.005
  • Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA Khvostov G
    NUCLEAR ENGINEERING AND DESIGN 328, 36 (2018).
    DOI: 10.1016/j.nucengdes.2017.12.028
  • Monte Carlo nuclear data adjustment via integral information Rochman D, Bauge E, Vasiliev A, Ferroukhi H, Pelloni S, Koning AJ, Sublet JCh
    The European Physical Journal Plus 133, 537 (2018).
    DOI: 10.1140/epjp/i2018-12361-x
  • Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell Papadionysiou M, Perret G, Zboray R, Adams R, Mosset J-B
    NUCLEAR ENGINEERING AND DESIGN 126, 118 (2018).
    DOI: 10.1016/j.nucengdes.2018.03.033
  • Nuclear data correlation between different isotopes via integral information Rochman Dimitri A, Bauge E, Vasiliev A, Ferroukhi H, Perret G
    EPJ Nuclear Sciences & Technologies 4, 7 (2018).
    DOI: 10.1051/epjn/2018006
  • On the characteristics of the flow and heat transfer in the core bypass region Clifford i, Pecchia M, Puragliesi R, Vasiliev A, Ferroukhi H
    NUCLEAR ENGINEERING AND DESIGN 128, 117 (2018).
    DOI: 10.1016/j.nucengdes.2018.01.039
  • PIV measurements in the vicinity of a steam sparger in the PANDA facility Kapulla R, Uong D, Zimmer C, Paladino D
    NUCLEAR ENGINEERING AND DESIGN 336, 112 (2018).
    DOI: 10.1016/j.nucengdes.2017.07.003
  • Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments Pelloni S, Rochman D
    ANNALS OF NUCLEAR ENERGY 121, 361 (2018).
    DOI: 10.1016/j.anucene.2018.07.043
  • SiC cladding thermal conductivity requirements for normal operation and LOCA conditions Cozzo C, Rahman S
    PROGRESS IN NUCLEAR ENERGY 283, 278 (2018).
    DOI: 10.1016/j.pnucene.2018.03.016
  • Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor Vitullo F, Krepel J, Kalilainen J, Prasser H, Pautz A
    International Conference on Nuclear Engineering, Proceedings -, - (2018).
    DOI: 10.1115/ICONE26-81082
  • Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments Siefman D, Hursin M, Rochman D, Pelloni S, Pautz A
    The European Physical Journal Plus 133, 429 (2018).
    DOI: 10.1140/epjp/i2018-12303-8
  • Subchannel modeling of single rod bowing in a bundle geometry Mukin R, Puragliesi R, Pecchia M, Seidl M
    NUCLEAR ENGINEERING AND DESIGN 340, 347 (2018).
    DOI: 10.1016/j.nucengdes.2018.09.032
  • Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu Noguere G, Tommasi J, Privas E, Schmidt KH, Rochman D
    The European Physical Journal Plus 133, 99 (2018).
    DOI: 10.1140/epjp/i2018-11926-y
  • Technical note: On modelling central void formation in LWR fuel pellets due to high-temperature restructuring Khvostov G
    Nuclear Engineering and Technology , S1738573318303887 (2018).
    DOI: 10.1016/j.net.2018.07.003
  • Testing of a sCVD diamond detection system in the CROCUS reactor Hursin M, Weiss C, Frajtag P, Lamirand V, Perret G, Kavrigin P, Pautz A, Griesmayer E
    EUROPEAN PHYSICAL JOURNAL A 54, 82 (2018).
    DOI: 10.1140/epja/i2018-12519-1
  • Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data Rochman Dimitri A, Vasiliev A, Dokhane A, Ferroukhi H
    EPJ Nuclear Sciences & Technologies 4, 6 (2018).
    DOI: 10.1051/epjn/2018005
  • Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes Bousbia Salah A, Ceuca SC, Puragliesi R, Mukin R, Grahn A, Kliem S, Vlassenbroeck J, Austregesilo H
    NUCLEAR TECHNOLOGY , 1 (2018).
    DOI: 10.1080/00295450.2018.1461517
  • Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments Dokhane A, Grandi G, Vasiliev A, Rochman D, Ferroukhi H
    ANNALS OF NUCLEAR ENERGY 184, 178 (2018).
    DOI: 10.1016/j.anucene.2018.04.022

2017

  • A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses Pecchia Marco, Vasiliev Alexander, Ferroukhi Hakim, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 105, 121-132 (2017).
    DOI: 10.1016/j.anucene.2017.03.008
  • Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone Dokhane A, Judd J, Gajev I, Zerkak O, Ferroukhi H, Kozlowski T
    ANNALS OF NUCLEAR ENERGY 102, 190-199 (2017).
    DOI: 10.1016/j.anucene.2016.12.015
  • Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
    PROGRESS IN NUCLEAR ENERGY , 1 (2017).
    DOI: 10.1016/j.pnucene.2017.03.018
  • Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X Aures A, Bostelmann F, Hursin M, Leray O
    ANNALS OF NUCLEAR ENERGY 101, 262-269 (2017).
    DOI: 10.1016/j.anucene.2016.11.025
  • Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores Li J, Rochman D, Vasiliev A, Ferroukhi H, Herrero J, Pautz A, Seidl M, Janin D
    ANNALS OF NUCLEAR ENERGY 110, 1023-1029 (2017).
    DOI: 10.1016/j.anucene.2017.08.022
  • Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores Rochman D, Mala P, Ferroukhi H, Vasiliev A, Seidl M, Janin D, Li J
    M&C 2017 International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P286, 1 (2017).
  • Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics Griffin P, Rochman D, Koning A
    EPJ Web of Conferences 146, 02008 (2017).
    DOI: 10.1051/epjconf/201714602008
  • Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances Helgesson P, Sjostrand H, Koning A J, Ryden J, Rochman D, Alhassan E, Pomp S
    PROGRESS IN NUCLEAR ENERGY 96, 76-96 (2017).
    DOI: 10.1016/j.pnucene.2016.11.006
  • Correlation nu-sigma-chi in the fast neutron range via integral information Rochman D, Baugne E, Vasiliev A, Ferroukhi H
    EPJ Web of Conferences 3, 14 (2017).
    DOI: 10.1051/epjn/2017009
  • Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19 Hursin M, Bogetic S, Dohkane A, Canepa S, Zerkak O, Ferroukhi H, Pautz A
    ANNALS OF NUCLEAR ENERGY 101, 559-575 (2017).
    DOI: 10.1016/j.anucene.2016.11.001
  • Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor Fiorina C, Hursin M, Pautz A
    ANNALS OF NUCLEAR ENERGY 101, 419-428 (2017).
    DOI: 10.1016/j.pnucene.2017.03.018
  • IAEA Neutronics Benchmark for EBR-II SHRT-45R Vezzoni B, van Rooijen W-F-G, Fei T, Zhang Y, Marchetti M, Balestra P, Parisi C
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 070 (2017).
  • Improving Activation Cross Sections for Fusion Applications Dzysiuk N, Koning AJ, Rochman D, Fischer U
    FUSION SCIENCE AND TECHNOLOGY 73, 13 (2017).
    DOI: 10.1080/15361055.2017.1372682
  • Kinetic Parameter Measurements in the MINERVE Reactor Perret G, Geslot B, Gruel A, Blaise P, Di-Salvo J, De Izarra G, Jammes Ch, Hursin M, Pautz A
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE 64, 724 (2017).
    DOI: 10.1109/TNS.2016.2637569
  • Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles Leray O, Ferroukhi H, Hursin M, Vasiliev A, Rochman D
    ANNALS OF NUCLEAR ENERGY 110, 547-559 (2017).
    DOI: 10.1016/j.anucene.2017.07.006
  • Monte Carlo simulation of scintillation detector for spent fuel characterization in a hot cell Papadionysiou M, Perret G, Zboray R, Adams R
    ANS Student Conference 2017, April 6-9, 2017, Pittsburgh, PA, USA , (2017).
  • NEW INSIGHTS IN THE FUEL GRAIN SUBDIVISION DURING IN-PLANT IRRADIATION UP TO HIGH BURN-UP Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson VA
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea -, - (2017).
  • Nodal and Pin-by-pin Calculations Comparison with Codes SIMULATE-5 and DYN3D Mala P, Pautz A, Canepa S, Ferroukhi H
    M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P010, 1 (2017).
  • Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core Rochman D, Leray O, Hursin M, Ferroukhi H, Vasiliev A, Aures A, Bostelmann F, Zwermann W, Cabellos O, Diez C J, Dyrda J, Garcia-Herranz N, Castro E, van der Marck S, Sjostrand H, Hernandez A, Fleming M, Sublet J -Ch, Fiorito L
    NUCLEAR DATA SHEETS 139, 1-76 (2017).
    DOI: 10.1016/j.nds.2017.01.001
  • Nuclear Data Uncertainty Decomposition for SPERT-III RIA Experiments using SIMULATE-3K and SHARK-X Dokhane A, Grandi G, Leray O, Rochman D, Vasiliev A, Ferroukhi H
    M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P236, 1 (2017).
  • Post-Dryout Heat Transfer Assessment of TRACE Aounallah Y
    37th Annual CNS Conference , 1 (2017).
  • Propagation of nuclear data uncertainties for fusion power measurements Sjöstrand H, Conroy S, Helgesson P, Hernandez S, Koning A, Pomp S, Rochman D
    EPJ Web of Conferences 146, 02034 (2017).
    DOI: 10.1051/epjconf/201714602034
  • Radiative neutron capture: Hauser Feshbach vs. statistical resonances Rochman D, Goriely S, Koning A J, Ferroukhi H
    PHYSICS LETTERS B 764, 109-113 (2017).
    DOI: 10.1016/j.physletb.2016.11.018
  • SIMULATE-3K Analyses of Neutron Noise Response to Fuel Assembly Vibrations and Thermal-Hydraulics Parameters Fluctuations Chionis D, Dokhane A, Belblidia L, Pecchia M, Girardin G, Ferroukhi H, Pautz A
    M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P289, 1 (2017).
  • SiC CLADDING BEHAVIOR: EXPERIMENTS AND MODELLING AT PSI Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, Pouchon M, Dai Y, Chen J C, Pytel M
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea 2017, 1 (2017).
  • TALYS/TENDL verification and validation processes: Outcomes and recommendations Fleming M, Sublet J, Gilbert Mark R, Koning A, Rochman D
    EPJ Web of Conferences 146, 02033 (2017).
    DOI: 10.1051/epjconf/201714602033
  • THERMAL HYDRAULIC ANALYSIS OF PWR ASSEMBLY BOWING USING SUBCHANNEL CODE COBRA-TF Mukin R, Clifford I, Ferroukhi H
    NURETH 17: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 20409 (2017).
  • THERMAL MIXING ASSESSMENT USING 3-D THERMAL-HYDRAULIC AND CFD CODES Mukin R, Puragliesi R, Ceuca SC, Austregesilo H, Bousbia Salah A
    NURETH 17: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 20714 (2017).
  • Testing the NURESIM platform on a PWR main steam line break benchmark Kliem S, Kozmenkov Y, Hadek J, Perin Y, Fouquet F, Bernard F, Sargeni A, Cuervo D, Sabater A, Sanchez-Cervera S, Garcia-Herranz N, Zerkak O, Ferroukhi H, Mala P
    NUCLEAR ENGINEERING AND DESIGN 321, 8-25 (2017).
    DOI: 10.1016/j.nucengdes.2017.05.028
  • UO2 fuel pin bowing effects on isotopic concentrations Li J, Rochman D, Herrero J, Vasiliev A, Ferroukhi H, Pautz A, Seidl M, Janin D
    ANNALS OF NUCLEAR ENERGY 105, 361-368 (2017).
    DOI: 10.1016/j.anucene.2017.03.038
  • Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly Leray O, Fiorito L, Rochman D, Ferroukhi H, Stankovskiy A, Van den Eynde G
    PROGRESS IN NUCLEAR ENERGY 1, 1 (2017).
    DOI: 10.1016/j.pnucene.2017.05.033
  • Worldwide activities Edwards L, LeBlanc D, Rodenburg C, Uhlí J, Dai Z, Lauritzen B, Allibert M, Heuer D, Laureau A, Merle E, Brovchenko M, Delpech S, Rineiski A, Vijayan PK, Dulera IV, Rama Rao A, Sinha RK, Waris A, Luzzi L, Cammi A, Yoshioka R, Kinoshita M, Lee D, Jeong Y, Kloosterman JL, Disen E, Ponomarev L, Boyes W, Pázsit I, Krepel J, Nichenko S, Hombourger B, Pautz A, Prasser M, Erbay LB, Scott I, Hodgson Z, Bakai AS, Lackowski V, Kutsch J, Greaves ED, Sajo-Bohus L
    Molten Salt Reactors and Thorium Energy , 635 (2017).
    DOI: 10.1016/B978-0-08-101126-3.00026-9

2016

  • A Bayesian Monte Carlo method for fission yield covariance information Rochman D, Leray O, Vasiliev A, Ferroukhi H, Koning A J, Fleming M, Sublet J C
    ANNALS OF NUCLEAR ENERGY 95, 125-134 (2016).
    DOI: 10.1016/j.anucene.2016.05.005
  • Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels Brankov Vladimir, Khvostov Grigori, Mikityuk Konstantin, Pautz Andreas, Restani Renato, Abolhassani Sousan, Ledergerber Guido, Wiesenack Wolfgang
    NUCLEAR ENGINEERING AND DESIGN 305, 559-568 (2016).
    DOI: 10.1016/j.nucengdes.2016.06.021
  • Analysis of selected Halden overpressure tests using the FALCON code Khvostov G, Wiesenack W
    NUCLEAR ENGINEERING AND DESIGN 310, 395-409 (2016).
    DOI: 10.1016/j.nucengdes.2016.10.033
  • Bayesian Calibration of Thermal-Hydraulics Model with Time-Dependent Output Wicaksono D, Zerkak O, Pautz A
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0491 (2016).
  • Bubble reconstruction method for wire-mesh sensors measurements Mukin RV
    EXPERIMENTS IN FLUIDS 57, - (2016).
    DOI: 10.1007/s00348-016-2220-y
  • Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data Brankov Vladimir, Khvostov Grigori, Mikityuk Konstantin, Pautz Andreas, Wiesenack Wolfgang
    NUCLEAR ENGINEERING AND DESIGN 300, 97-106 (2016).
    DOI: 10.1016/j.nucengdes.2015.11.023
  • Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO2 Fuel Assembly Leray O, Fiorito L, Rochman D, Ferroukhi H, Pautz A, Stankovskiy A, Van Den Eynde G
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Developing an in situ EXAFS experiment of microwave-induced gelation Cozzo C, Ishizaki K, Pouchon MA, Vaucher S
    JOURNAL OF SOL-GEL SCIENCE AND TECHNOLOGY 78, 507 (2016).
    DOI: 10.1007/s10971-016-3992-5
  • Evaluation of Deterministic Sampling for Uncertainty Quantification in a Probabilistic Accident Analysis Model Rahman S, Karanki DR, Wicaksono D, Zerkak O, Dang VN
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0291 (2016).
  • Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for the CROCUS Reactor Rais A, Hursin M, Perret G, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Fission yield covariances for JEFF: a Bayesian Monte Carlo method Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, Ferroukhi H
    International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
  • Full Core LOCA Analysis for BWR/6 - Methodology and First Results Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, Brankov V, Gorzel A
    TopFuel 2016: LWR Fuels with Enhanced Safety and Performance (Sep 11-16, 2016, Boise, Idaho, U.S.A.) 1, 1135 (2016).
  • Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model Using the TRACE Code Wicaksono Damar, Zerkak Omar, Pautz Andreas
    NUCLEAR SCIENCE AND ENGINEERING 184, 400-429 (2016).
    DOI: 10.13182/NSE16-37
  • Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures F, Zwermann W
    ND2013: International Conference on Nuclear Data for Science and Technology 2016, 1 (2016).
  • Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal Herrero J, Rochman D, Leray O, Vasiliev, Pecchia M, Ferroukhi H, Caruso S
    International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
  • Influence of URANS Turbulence Models on In-Vessel Flow Mixing During Cold Leg Accumulator Injection Puragliesi R, Zerkak O, Pautz A
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0292 (2016).
  • KMacs, AModular Adaptable Core Simulator Zilly M, Küntzel M, Aures A, Hannstein V, Velkov K, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Key Findings from the Artist Project on Aerosol Retention in a Dry Steam Generator Dehbi A, Suckow D, Lind T, Guentay S, Danner S, Mukin R
    Nuclear Engineering and Technology 48, 870 (2016).
    DOI: 10.1016/j.net.2016.06.001
  • Localized neutron flux assessment and verification studies using MCNPX PWR full core model Vasiliev A, Ferroukhi H, Pecchia M, Pautz A
    ANNALS OF NUCLEAR ENERGY 92, 317-332 (2016).
    DOI: 10.1016/j.anucene.2016.01.026
  • Modeling and Analysis of selected OECD PKL3 Station-Blackout Experiments using TRACE Mukin R, Zerkak O, Pautz A
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0310 (2016).
  • Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation Rochman D, Vasiliev A, Ferroukhi H, Zhu T, van der Marck S C, Koning A J
    ANNALS OF NUCLEAR ENERGY 92, 150-160 (2016).
    DOI: 10.1016/j.anucene.2016.01.042
  • Nuclear data uncertainty propagation on spent fuel nuclide compositions Leray O, Rochman D, Grimm P, Ferroukhi H, Vasiliev A, Hursin M, Perret G, Pautz A
    ANNALS OF NUCLEAR ENERGY 94, 603-611 (2016).
    DOI: 10.1016/j.anucene.2016.03.023
  • On Causality Analysis of Nuclear Reactor Noise using Partial Directed Coherence Chionis D, Dokhane A, Ferroukhi H, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology Alhassan E, Sjoestrand H, Helgesson P, Oesterlund M, Pomp S, Koning A J, Rochman D
    PROGRESS IN NUCLEAR ENERGY 88, 43-52 (2016).
    DOI: 10.1016/j.pnucene.2015.11.015
  • Po-210 poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat Froidevaux Pascal, Bochud Francois, Baechler Sebastien, Castella Vincent, Augsburger Marc, Bailat Claude, Michaud Katarzyna, Straub Marietta, Pecchia Marco, Jenk Theo M, Uldin Tanya, Mangin Patrice
    FORENSIC SCIENCE INTERNATIONAL 259, 1-9 (2016).
    DOI: 10.1016/j.forsciint.2015.09.019
  • Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels Chollet M, Krsjak V, Cozzo C, Bertsch J
    EPJ Nuclear Sci. Technol. 3, 3 (2016).
    DOI: 10.1051/epjn/2016040
  • Re-evaluation of the thermal neutron capture cross section of Nd-147 Rochman D, Leray O, Perret G, Vasiliev A, Ferroukhi H, Koning A J
    ANNALS OF NUCLEAR ENERGY 94, 612-617 (2016).
    DOI: 10.1016/j.anucene.2016.03.024
  • Recent research activities on high temperature pebble bed reactors at PSI Kalilainen J, Prasser HM, Lind T, Krepel J, Schenler W
    HTR 2016: Proceedings of the High Temperature Reactor Conference Las Vegas, United States, November 6-10, 2016 8, 135-140 (2016).
  • Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark Herrero Jose J, Vasiliev Alexander, Pecchia Marco, Ferroukhi Hakim, Caruso Stefano
    ANNALS OF NUCLEAR ENERGY 87, 48-57 (2016).
    DOI: 10.1016/j.anucene.2015.08.014
  • Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation Helgesson P, Sjostrand H, Koning A J, Ryden J, Rochman D, Alhassan E, Pomp S
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 807, 137-149 (2016).
    DOI: 10.1016/j.nima.2015.10.024
  • Selecting benchmarks for reactor simulations: An application to a lead fast reactor Alhassan E, Sjostrand H, Helgesson P, Osterlund M, Pomp S, Koning A J, Rochman D
    ANNALS OF NUCLEAR ENERGY 96, 158-169 (2016).
    DOI: 10.1016/j.anucene.2016.05.033
  • Simulation of Level-Swell Experiments with TRACE Aounallah Y
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0125 (2016).
  • Solution of the Beavrs Benchmark using CASMO-5 / SIMULATE-5 Code Sequence Bykov V, Vasiliev A, Ferroukhi H, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Steady-state CFD simulations of an EPR (TM) reactor pressure vessel: A validation study based on the JULIETTE experiments Puragliesi R, Zhou L, Zerkak O, Pautz A
    NUCLEAR ENGINEERING AND DESIGN 300, 41-56 (2016).
    DOI: 10.1016/j.nucengdes.2015.12.025
  • System Code Validation Series based on a Consistent Plant Nodalisation of the ROSA/LSTF Integral Test Facility using TRACE v5.0 Patch 4 Clifford I, Zerkak O, Pautz A
    NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0424 (2016).
  • Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data-Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations Zhu Ting, Vasiliev Alexander, Ferroukhi Hakim, Rochman Dimitri, Pautz Andreas
    NUCLEAR SCIENCE AND ENGINEERING 184, 69-83 (2016).
    DOI: 10.13182/NSE14-142
  • The TENDL library: hope, reality and future Rochman D, Koning AJ, Sublet JCh, Fleming M, Bauge E, Hilaire S, Romain P, Morillon B, Duarte H, Goriely S, van der Marck SC, Sjöstrand H, Pomp S, Dzysiuk N, Cabellos O, Ferroukhi H, Vasiliev A
    International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
  • The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part II: Thorium fuel cycle Lindley A, Fiorina C, Gregg R, Franceschini F, Parks GT
    PROGRESS IN NUCLEAR ENERGY 87, 144 (2016).
    DOI: 10.1016/j.pnucene.2014.11.016
  • Towards a Consolidated Approach for the Assessment of Evaluation Models of Nuclear Power Reactors Epiney A, Canepa S, Zerkak O, Ferroukhi H
    NUCLEAR TECHNOLOGY 196, 223-237 (2016).
    DOI: 10.13182/NT16-47
  • Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX Hursin Mathieu, Scriven Michael, Perret Gregory, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 91, 48-58 (2016).
    DOI: 10.1016/j.anucene.2015.12.035
  • Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data Pecchia Marco, Wicaksono Damar, Grimm Peter, Vasiliev Alexander, Perret Gregory, Ferroukhi Hakim, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 97, 153-164 (2016).
    DOI: 10.1016/j.anucene.2016.07.001
  • Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions Perret G, Blaise P, Messaoudi N, Geslot B, Wagemans J, Baeten P, Kochetkov A, Pautz A
    ANNALS OF NUCLEAR ENERGY 97, 165 (2016).
    DOI: 10.1016/j.anucene.2016.07.015
  • Validation of SIMULATE-3K against SPERT-III Ria Experiments with Quantification of Nuclear Data Uncertainties Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K Dokhane A, Ferroukhi E, Pautz A
    ANNALS OF NUCLEAR ENERGY 96, 344-353 (2016).
    DOI: 10.1016/j.anucene.2016.06.016
  • Verification of the New Implementations in SHARK-X for Reactivity Coefficients and Relative Reactivity Worth UQ Hursin M, Siefman D, Perret G, Grimm P, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).

2015

  • A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics Zanetti Matteo, Cammi Antonio, Fiorina Carlo, Luzzi Lelio
    PROGRESS IN NUCLEAR ENERGY 83, 82-98 (2015).
    DOI: 10.1016/j.pnucene.2015.02.014
  • A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT Aufiero M, Bidaud A, Hursin M, Leppaenen J, Palmiotti G, Pelloni S, Rubiolo P
    ANNALS OF NUCLEAR ENERGY 85, 245 (2015).
    DOI: 10.1016/j.anucene.2015.05.008
  • Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping Pecchia Marco, Vasiliev Alexander, Leray Olivier, Ferroukhi Hakim, Pautz Andreas
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 52, 1084-1092 (2015).
    DOI: 10.1080/00223131.2015.1032382
  • Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event Demeshko M, Dokhane A, Washio T, Ferroukhi H, Kawahara Y, Aguirre C
    ANNALS OF NUCLEAR ENERGY 75, 645-657 (2015).
    DOI: 10.1016/j.anucene.2014.08.045
  • Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR Pecchia Marco, Parisi Carlo, D'Auria Francesco, Mazzantini Oscar
    ANNALS OF NUCLEAR ENERGY 85, 271-278 (2015).
    DOI: 10.1016/j.anucene.2015.05.023
  • Assessment of OpenFOAM CFD Toolbox for Gravity Driven Mixing Flows in a Reactor Pressure Vessel Puragliesi R, Zhou Q, Zerkak O, Pautz A
    NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 952 (2015).
  • Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions Hursin M, Downar T, Yoon J, Joo H
    ANNALS OF NUCLEAR ENERGY 87, 356 (2015).
  • Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution Hursin M, Joo H, Downar T
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 3, 2394 (2015).
  • BWR Full Core Analysis with SERPENT/SIMULATE-3 Hybrid Stochastic/Determinstic Code Sequence Hursin M, Rossinelli L, Ferroukhi H, Pautz A
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 63, 1 (2015).
  • Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor Kriventsev V, Rineiski A, Prang W, Perez-Martin S, Mikityuk K, Khvostov G
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm , (2015).
  • Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project Jimenez G, Herrero JJ, Gommlich A, Kliem S, Cuervo D, Jimenez J
    ANNALS OF NUCLEAR ENERGY 84, 86-97 (2015).
    DOI: 10.1016/j.anucene.2014.11.002
  • COMPLINK: A Versatile Tool for Automatizing the Representation of Material Data in MCNP Models Pecchia M, Herrero J, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
    ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 513 (2015).
  • Computational Scheme for Burnup Credit applied to Long Term Waste Disposal Herrero J, Pecchia M, Ferroukhi H, Canepa S, Vasiliev A, Caruso S
    ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 1783 (2015).
  • Criticality Safety Evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology Pecchia Marco, Vasiliev Alexander, Ferroukhi Hakim, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 83, 226-235 (2015).
    DOI: 10.1016/j.anucene.2015.03.052
  • Delayed Neutron Fraction and Prompt Decay Constant Measurement in the MINERVE Reactor using the PSI Instrumentation Perret G
    ANIMMA 2015: Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 20-24 April 2015, Lisbon 1, 1 (2015).
  • Development, Verification and Test Application of a Hybrid CASMO-5/SERPENT Depletion Scheme Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A, Perrier H
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 2015, 1 (2015).
  • Fuel cycle analysis of a molten salt reactor for breed-and-burn mode Hombourger B, Krepel J, Mikityuk K, Pautz A
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor Siefman Daniel J, Girardin Gaetan, Rais Adolfo, Pautz Andreas, Hursin Mathieu
    ANNALS OF NUCLEAR ENERGY 85, 434-443 (2015).
    DOI: 10.1016/j.anucene.2015.05.004
  • GeN-Foam: a novel OpenFOAM (R) based multi-physics solver for 2D/3D transient analysis of nuclear reactors Fiorina Carlo, Clifford Ivor, Aufiero Manuele, Mikityuk Konstantin
    NUCLEAR ENGINEERING AND DESIGN 294, 24-37 (2015).
    DOI: 10.1016/j.nucengdes.2015.05.035
  • Improving neutronics simulations and uncertainties via a selection of nuclear data Rochman D, Koning A J, van der Marck S C
    EUROPEAN PHYSICAL JOURNAL A 51, 182 (2015).
    DOI: 10.1140/epja/i2015-15182-0
  • Methodology for Global Sensitivity Analysis of Transient Code Output applied to a Reflood Experiment Model using TRACE Wicaksono D, Zerkak O, Pautz A
    NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 4862 (2015).
  • Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    Science and Technology of Nuclear Installations 2015, 237646 (2015).
    DOI: 10.1155/2015/237646
  • Modeling of Axial Distribution of Released Fission Gas in KKL BWR Fuel Rods during Base Irradiation Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm 1, 609 (2015).
  • Modelling guidelines for core exit temperature simulations with system codes Freixa J, Martinez-Quiroga V, Zerkak O, Reventos F
    NUCLEAR ENGINEERING AND DESIGN 286, 116-129 (2015).
    DOI: 10.1016/j.nucengdes.2015.02.003
  • Multi-scale approach to advanced fuel modelling for enhanced safety Ribeiro Fabienne, Khvostov Grigori
    PROGRESS IN NUCLEAR ENERGY 84, 24-35 (2015).
    DOI: 10.1016/j.pnucene.2015.03.022
  • NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification Zhu Ting, Vasiliev Alexander, Ferroukhi Hakim, Pautz Andreas, Tarantola Stefano
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 52, 1000-1007 (2015).
    DOI: 10.1080/00223131.2015.1040864
  • NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method Zhu Ting, Vasiliev Alexander, Ferroukhi Hakim, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 75, 713-722 (2015).
    DOI: 10.1016/j.anucene.2014.09.013
  • Neutron production and thermal moderation at the PSI UCN source Becker H, Bison G, Blau B, Chowdhuri Z, Eikenberg J, Fertl M, Kirch K, Lauss B, Perret G, Reggiani D, Ries D, Schmidt-Wellenburg P, Talanov V, Wohlmuther M, Zsigmond G
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 777, 20-27 (2015).
    DOI: 10.1016/j.nima.2014.12.091
  • Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor Hombourger B, Krepel J, Mikityuk K, Pautz A
    Journal of Nuclear Engineering and Radiation Science 1, 011009 (2015).
    DOI: 10.1115/1.4026401
  • Particle deposition modeling in the secondary side of a steam generator bundle model Mukin R, Dehbi A
    NUCLEAR ENGINEERING AND DESIGN , (2015).
    DOI: 10.1016/j.nucengdes.2015.09.001
  • Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels Chollet M, Krsjak V, Cozzo C, Bertsch J
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm Paper A0109, (2015).
  • Preparation of Pin-By-Pin Nuclear Libraries with Superhomogenization Method for Ntracer and Dort Core Calculations Mala P, Canepa S, Ferroukhi H, Pautz A
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 2015, 1 (2015).
  • Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study Based on a Station Blackout Scenario Rahman S, Karanki DR, Epiney A, Zerkak O, Dang VN
    NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 5734 (2015).
  • Review of multi-physics temporal coupling methods for analysis of nuclear reactors Zerkak Omar, Kozlowski Tomasz, Gajev Ivan
    ANNALS OF NUCLEAR ENERGY 84, 225-233 (2015).
    DOI: 10.1016/j.anucene.2015.01.019
  • Scalability Benchmarking Methodology for Hybrid Parallel Core Calculations with the Code nTRACER Canepa S, Krack M, Ferroukhi H, Pautz A
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 2015, 1 (2015).
  • Sodium Void Map Preparation for the Safety Analysis of Sodium-cooled Fast Reactors by Using the Monte Carlo Code Serpent Pelloni S, Aufiero M, Bortot S, Krepel J, Mikityuk K, Panadero A-L, Pautz A, Sciora P
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • TOWARDS A CONSOLIDATED APPROACH FOR THE VALIDATION OF PLANT SYSTEM CODES AND MODELS: CASE STUDY FOR A BWR FAST DEPRESSURISATION EVENT Epiney A, Canepa S, Zerkak O, Ferroukhi H
    NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 1 (2015).
  • TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Koslowski T
    NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 4757 (2015).
  • Toward Reanalysis of the Tight-Pitch HCLWR-PROTEUS Phase II Experiments Perret G, Vlassopoulos E, Hursin M, Pautz A
    Wonder 2015: Fourth International Workshop on Nuclear Data Evaluation for Reactor Applications 1, 1 (2015).
  • Towards Application of Neutron Cross-Section Uncertainty Propagation Capability in the Criticality Safety Methodology Vasiliev A, Rochman D, Zhu T, Pecchia M, Ferroukhi H, Pautz A
    ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 606 (2015).
  • Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data Dupre A, Vasiliev A, Ferroukhi H, Pautz A
    ANNALS OF NUCLEAR ENERGY 85, 820-829 (2015).
    DOI: 10.1016/j.anucene.2015.06.040
  • Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis Hursin Mathieu, Perret Gregory, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 77, 300-309 (2015).
    DOI: 10.1016/j.anucene.2014.11.019

2014

  • AN INNOVATIVE APPROACH TO DYNAMICS MODELING AND SIMULATION OF THE MOLTEN SALT RECTOR EXPERIMENT Zanetti M, Luzzi L, Cammi A, Fiorina C
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104090 (2014).
  • ANALYSIS OF THE OECD/NEA OSKARSHAMN-2 FEEDWATER TRANSIENT AND STABILITY BENCHMARK WITH SIMULATE-3K Dokhane A, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1101708 (2014).
  • Analysis of Axial Fuel Relocation Based on Gamma Scan Data from OECD Halden Reactor Project LOCA Tests Brankov V, Khvostov G, Mikityuk K, Pautz A, Eitrheim K
    WRFPM 2014 Proceedings, Sendai, Japan CD-ROM, 100041 (2014).
  • Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k(eff) Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark Zhu T, Vasiliev A, Ferroukhi H, Pautz A
    NUCLEAR DATA SHEETS 118, 453-455 (2014).
    DOI: 10.1016/j.nds.2014.04.104
  • Assessment of CFD URANS Models for Buoyancy Driven Mixing Flows Based on ROCOM Experiments Puragliesi R, Zerkak O, Pautz A
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1179 (2014).
  • Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser Papini Davide, Adamsson Carl, Andreani Michele, Prasser Horst-Michael
    NUCLEAR ENGINEERING AND DESIGN 278, 542-557 (2014).
    DOI: 10.1016/j.nucengdes.2014.08.007
  • Assessment of TRACE against Single-Tube Post-Dryout Heat Transfer Experiments Aounallah Y
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1192 (2014).
  • CASMO-4E AND CASMO-5 ANALYSIS OF THE ISOTOPIC COMPOSITIONS OF THE LWR-PROTEUS PHASE II BURNT PWR UO2 FUEL SAMPLES Grimm P, Perret G, Ferroukhi H
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104066 (2014).
  • Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks Zhu T, Rochman D, Vasiliev A, Ferroukhi H, Wieselquist W, Pautz A
    NUCLEAR DATA SHEETS 118, 388-391 (2014).
    DOI: 10.1016/j.nds.2014.04.088
  • EFFECTS OF ADVANCED RADIAL SUBMESHING METHODS ON PIN POWER RECONSTRUCTION FOR AN EPR CORE DESIGN Mala P, Canepa S, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105669 (2014).
  • Exploring Variability in Reflood Simulation Results: An Application of Functional Data Analysis Wicaksono D, Zerkak O, Pautz A
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1208 (2014).
  • Hybrid spectrum molten salt reactor Krepel J, Mikityuk K, Hombourger B, Pautz A, Zanetti M, Aufiero M, Luzzi L
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future , (2014).
  • NEW PSI METHODOLOGY FOR MANUFACTURING AND TECHNOLOGICAL UNCERTAINTY QUANTIFICATION Pecchia M, Vasiliev A, Leray O, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105694 (2014).
  • Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5 Rossinelli L, Hursin M, Ferroukhi H, Pautz A
    ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
  • Nuclear Data Library Effects on Fast to Thermal Flux Shapes Around PWR Control Rod Tips Vasiliev A, Ferroukhi H, Zhu T, Pautz A
    NUCLEAR DATA SHEETS 118, 575-578 (2014).
    DOI: 10.1016/j.nds.2014.04.139
  • On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology Dokhane A, Ferroukhi H, Pautz A
    ANNALS OF NUCLEAR ENERGY 67, 21-30 (2014).
    DOI: 10.1016/j.anucene.2013.11.006
  • PARAMETRIC LATTICE STUDY OF A GRAPHITE-MODERATED MOLTEN SALT REACTOR Hombourger B, Krepel J, Mikityuk K, Pautz A
    ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 22, 31050 (2014).
  • PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    IGORR: International Group on Research Reactors, 17-21 November 2014, Bariloche, Argentina 1, 1 (2014).
  • PINPOWER UNCERTAINTY QUANTIFICATION OF LWR-PROTEUS PHASE III EXPERIMENTS Hursin M, Scriven M, Perret G, Grimm P, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1099077 (2014).
  • Post-test Analysis of OECD/NEA ROSA-2 Test 4 using TRACE Clifford I, Zerkak O, Pautz A
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1182 (2014).
  • QUANTIFICATION OF CODE, LIBRARY AND CROSS-SECTION UNCERTAINTY EFFECTS ON THE VOID REACTIVITY COEFFICIENT OF A BWR UO2 ASSEMBLY Leray O, Grimm P, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1100815 (2014).
  • Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly Perrier H, Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
  • Sensitivity Analysis of a Bottom Reflood Simulation using the Morris Screening Method Wicaksono D, Zerkak O, Pautz A
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1205 (2014).
  • Simulation of flow in the secondary side of a steam generator bundle Mukin RV, Dehbi A
    CFD4NRS-5: Proceedings of the OECD/NEA & IAEA Workshop on Computational Fluid Dynamics for Nuclear Safety Research, ETH Zuerich, Switzerland, Sep. 9-11, 2014 1, 1 (2014).
  • Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools Ferroukhi H, Leray O, Hursin M, Vasiliev A, Perret G, Pautz A
    NUCLEAR DATA SHEETS 118, 498-501 (2014).
    DOI: 10.1016/j.nds.2014.04.117
  • The Development and Implementation of a One-Dimensional S-n Method in the 2D-1D Integral Transport Solution Hursin M, Collins B, Xu Y, Downar T
    NUCLEAR SCIENCE AND ENGINEERING 176, 186-200 (2014).
    DOI: 10.13182/NSE12-4
  • Treatment of Epistemic and Aleatory Uncertainties in DET Simulations: Computational Framework with ADS-TRACE Rahman S, Karanki DR, Zerkak O, Dang VN
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1173 (2014).
  • UNCERTAINTY AND SENSITIVITY ANALYSIS OF OECD/NEA UAM FUEL THERMAL BEHAVIOUR BENCHMARK USING A FALCON/URANIE METHODOLOGY Yun Y, Leray O, Ferroukhi H
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105847 (2014).
  • UNCERTAINTY QUANTIFICATION OF SPENT FUEL NUCLIDE COMPOSITIONS DUE TO CROSS SECTIONS, DECAY CONSTANTS AND FISSION YIELDS Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104088 (2014).
  • UPDATED VALIDATION OF THE PSI CRITICALITY SAFETY EVALUATION METHODOLOGY USING MCNPX2.7 AND ENDF/B-VII.1 Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105709 (2014).
  • Uncertainty- and Sensitivity Analysis of COBRA-TF for the Simulation of Selected OECD/NRC BFBT Void Experiments Epiney A, Zerkak O, Pautz A
    NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1196 (2014).
  • VALIDATION OF TWO MONTE CARLO CODES FOR LWR BURNUP CALCULATIONS Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105825 (2014).
  • VERIFICATION OF A REACTOR PHYSICS CALCULATION SCHEME FOR THE CROCUS REACTOR Hursin M, Siefman D, Rais A, Girardin G, Pautz A
    ITMSR-3: 3rd International Technical Meeting on Small Reactors, 5-7 Nov 2015, Ottawa, Canada 1, 1 (2014).
  • Validation Enhancements of the PSI Fast Neutron Fluence Computational Scheme using Operational PWR Experimental Data Dupre A, Vasiliev A, Ferroukhi H, Pautz A
    ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
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