LRS Publication List (since 2012)

2018

  • Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A
    ANNALS OF NUCLEAR ENERGY 111, 141 (2018).
    DOI: 10.1016/j.anucene.2017.08.061

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
  • Analysis of the U L-3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations Bocharov Dmitry, Chollet Melanie, Krack Matthias, Bertsch Johannes, Grolimund Daniel, Martin Matthias, Kuzmin Alexei, Purans Juris, Kotomin Eugene
    PROGRESS IN NUCLEAR ENERGY 94, 187-193 (2017).
    DOI: 10.1016/j.pnucene.2016.07.017
  • Atomic-scale effects of chromium-doping on defect behaviour in uranium dioxide fuel Guo Zhexi, Ngayam-Happy Raoul, Krack Matthias, Pautz Andreas
    JOURNAL OF NUCLEAR MATERIALS 488, 160-172 (2017).
    DOI: 10.1016/j.jnucmat.2017.02.043
  • Benchmark Analyses of EBR-II Shutdown Heat Removal Tests Briggs L, Kriventsev V, Monti S, Hu W, Sui D, Su G, Maas L, Vezzoni B, Sarathy U-P, Del Nevo A, Petruzzi A, Zanino R, Ohira H, Van Rooijen W-F-G-, Morita K, Choi C, Shin A, Stempniewicz M, Rtischev N, Mikityuk K, Truong B
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 004 (2017).
  • 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 (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).
  • Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow Mambelli S, Mikityuk K, Panadero A-L
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 451 (2017).
  • Combined XAFS spectroscopy and ab initio study on the characterization of iron incorporation by montmorillonite Keri A, Daehn R, Krack M, Churakov S
    ENVIRONMENTAL SCIENCE & TECHNOLOGY 52, 1 (2017).
    DOI: 10.1021/acs.est.7b01670
  • 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
  • Comparison of fast reactors performance in the closed U-Pu and Th-U cycle Krepel J, Losa E
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 052 (2017).
  • Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems Pelloni S
    ANNALS OF NUCLEAR ENERGY 106, 33 (2017).
    DOI: 10.1016/j.anucene.2017.03.040
  • Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment Bates E, Zhang D, Truong B, Sui D, Hu W, Su G, Sumner T, Maas L, Vezzoni B, Marchetti M, Zanino R, Caron D, Van Rooijen W-V-G, Mochizuki H, Morita K, Choi C, Stempniewicz M, Rtischev N, Zhang Y, Mikityuk K
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 372 (2017).
  • 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
  • ESFR-SMART: new Horizon-2020 project on SFR safety Mikityuk K, Girardi E, Krepel J, Bubelis E, Fridman E, Rineiski A, Girault N, Payot F, Buligins L, Gerbeth G, Chauvin N, Latge C, Garnier JC
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 450 (2017).
  • 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
  • GEN IV Education and Training Initiative via Public Webinars Paviet P, Alekseev P, Fazio C, Fraton Mi, Hwang I, Kelly J, Liu X, Mihara T, Mikityuk K, Mpoza N, Nam Y, Pynn G, Renault C, Sun J
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 009 (2017).
  • 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).
  • IAEA?s Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview Batra C, Kriventsev V, Monti S, Briggs L, Hu W, Sui D, Su G, Maas L, Vezzoni B, Sarathy U-P, Del Nevo A, Petruzzi A, Zanino R, Ohira H, Van Rooijen W-F-G, Morita K, Choi C, Shin A, Stempniewicz M, Rtischev N, Mikityuk K, Bates E
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 361 (2017).
  • 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
  • Low-void-effect sodium-cooled core: Uncertainty of local sodium void reactivity as a result of nuclear data uncertainties Pelloni S, Panadero A-L, Mikityuk K, Pautz A
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 050 (2017).
  • 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).
  • 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).
  • Objectives and Status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM) Rimpault G, Buiron L, Stauff N-E, Kim T-K, Taiwo T-A, Lee Y-K, Aures A, Bostelmann F, Fridman E, Kereszturi A, Batki B, Kodeli I-A, Mikityuk K, Lopez R, Gomez A, Puente-Espel F, del Valle E, Peregudov A, Semenov M, Manturov G, Nakahara Y, Dyrda J, Ivanova T
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 220 (2017).
  • On the Feasibility of Breed-and-Burn Fuel Cycles in Molten Salt Reactors Hombourger B, Krepel J, Mikityuk K, Pautz A
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 388 (2017).
  • Periodic continuum solvation model integrated with first-principles calculations for solid surfaces Yin Wenjin, Krack Matthias, Li Xibo, Chen Lizhen, Liu Limin
    PROGRESS IN NATURAL SCIENCE-MATERIALS INTERNATIONAL 27, 283-288 (2017).
    DOI: 10.1016/j.pnsc.2017.03.003
  • Post-Dryout Heat Transfer Assessment of TRACE Aounallah Y
    37th Annual CNS Conference , 1 (2017).
  • 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).
  • Simulating Circulating-Fuel Fast Reactors with the Coupled TRACE-PARCS Code Pettersen E-E, Mikityuk K
    FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 059 (2017).
  • 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, Kozmenkow 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 , 1 (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
Top

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
  • A Progressive Incremental Adjustment Methodology for Cross-Section and Variance/Covariance Data Adjustment for Fast-Spectrum Systems Pelloni S
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride Bocharov Dmitry, Krack Matthias, Kalinko Aleksandr, Purans Juris, Rocca Francesco, Ali Shehab E, Kuzmin Alexei
    16TH INTERNATIONAL CONFERENCE ON X-RAY ABSORPTION FINE STRUCTURE (XAFS16) 712, UNSP 012009 (2016).
    DOI: 10.1088/1742-6596/712/1/012009
  • 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
  • Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform Fiorina Carlo, Kerkar Nordine, Mikityuk Konstantin, Rubiolo Pablo, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 96, 212-222 (2016).
    DOI: 10.1016/j.anucene.2016.05.023
  • Enumeration of static and dynamic neutron consumption D-factor for several selected reactors at equilibrium closed fuel cycle Krepel J, Losa, E
    ICAPP 2016: Proceedings of the International Congress on Advances in Nuclear Power Plants 2016 , (2016).
  • 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).
  • Interpretation of the U L-3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations Bocharov Dmitry, Chollet Melanie, Krack Matthias, Bertsch Johannes, Grolimund Daniel, Martin Matthias, Kuzmin Alexei, Purans Juris, Kotomin Eugene
    16TH INTERNATIONAL CONFERENCE ON X-RAY ABSORPTION FINE STRUCTURE (XAFS16) 712, (2016).
    DOI: 10.1088/1742-6596/712/1/012091
  • 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).
  • Neutronics Benchmark for EBR-II Shutdown Heat Removal Test SHRT-45R Fei T, Vezzoni B, Marchetti M, van Rooijen WFG, Zhang Y
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century , 221 (2016).
  • Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor Garcia-Herranz N, Panadero AL, Martinez A, Pelloni S, Mikityuk K, Pautz A
    ND2016: International Conference on Nuclear Data for Science and Technology , (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
  • Prebiotic NH3 Formation: Insights from Simulations Stirling Andras, Rozgonyi Tamas, Krack Matthias, Bernasconi Marco
    INORGANIC CHEMISTRY 55, 1934-1939 (2016).
    DOI: 10.1021/acs.inorgchem.5b02911
  • 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
  • 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).
  • Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels Zhang Y, Mikityuk K
    ANNALS OF NUCLEAR ENERGY 87, 761 (2016).
    DOI: 10.1016/j.anucene.2015.03.025
  • 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 EQL0D procedure for fuel cycle studies in molten salt reactor Hombourger B, Krepel J, Mikityuk K, Pautz A
    ICAPP 2016: Proceedings of the International Congress on Advances in Nuclear Power Plants 2016 , (2016).
  • The Effect of Excess Electron and hole on CO2 Adsorption and Activation on Rutile (110) surface Yin Wen-Jin, Wen Bo, Bandaru Sateesh, Krack Matthias, Lau M W, Liu Li-Min
    Scientific Reports 6, 23298 (2016).
    DOI: 10.1038/srep23298
  • 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 -- Part II: Thorium fuel cycle B A Lindley, C Fiorina, R Gregg, F Franceschini, G T Parks
    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).
Top

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
  • Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes Fiorina C, Mikityuk K
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • 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) , (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
  • CO2 Capture and Conversion on Rutile TiO2(110) in the Water Environment: Insight by First-Principles Calculations Yin Wen-Jin, Krack Matthias, Wen Bo, Ma Shang-Yi, Liu Li-Min
    JOURNAL OF PHYSICAL CHEMISTRY LETTERS 6, 2538-2545 (2015).
    DOI: 10.1021/acs.jpclett.5b00798
  • 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).
  • Comparison of Several Recycling Strategies and Relevant Fuel Cycles for Molten Salt Reactor Krepel J, Hombourger B, Fiorina C, Mikityuk K
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (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).
  • Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor Perko Zoltan, Pelloni Sandro, Mikityuk Konstantin, Ktepel Jiri, Szieberth Mate, Gaetan Girardin, Vrban Branislav, Lueley Jakub, Cerba Stefan, Halasz Mate, Feher Sandor, Reiss Tibor, Kloosterman Jan Leen, Stainsby Richard, Poette Christian
    PROGRESS IN NUCLEAR ENERGY 83, 460-481 (2015).
    DOI: 10.1016/j.pnucene.2014.09.016
  • 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).
  • Effects of stoichiometry on the defect clustering in uranium dioxide Ngayam-Happy Raoul, Krack Matthias, Pautz Andreas
    JOURNAL OF PHYSICS-CONDENSED MATTER 27, 455401 (2015).
    DOI: 10.1088/0953-8984/27/45/455401
  • European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients Bortot S, Alvarez-Velarde F, Fridman E, G Crusado I, G Herranz N, Lopez D, Mikityuk K, Panadero A-L, Pelloni S, Ponomarev A, Sciora P, Seubert A, Tsige-Tamirat H, Vasile A
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • Extension of the FAST code system for the modelling and simulation of MSR dynamics Zanetti M, Cammi A, Luzzi L, Krepel J, Mikityuk K
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (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
  • Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation Bertolus Marjorie, Freyss Michel, Dorado Boris, Martin Guillaume, Hoang Kiet, Maillard Serge, Skorek Richard, Garcia Philippe, Valot Carole, Chartier Alain, Van Brutzel Laurent, Fossati Paul, Grimes Robin W, Parfitt David C, Bishop Clare L, Murphy Samuel T, Rushton Michael J D, Staicu Dragos, Yakub Eugen, Nichenko Sergii, Krack Matthias, Devynck Fabien, Ngayam-Happy Raoul, Govers Kevin, Deo Chaitanya S, Behera Rakesh K
    JOURNAL OF NUCLEAR MATERIALS 462, 475-495 (2015).
    DOI: 10.1016/j.jnucmat.2015.02.026
  • Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor Krepel J, Pelloni S, Bortot S, Panadero A-L, Mikityuk K
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • 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) 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
  • On the ground state electronic structure of uranium dioxide Krack Matthias
    PHYSICA SCRIPTA 90, 094014 (2015).
    DOI: 10.1088/0031-8949/90/9/094014
  • On the use of the SPH method in nodal diffusion analyses of SFR cores Nikitin E, Fridman E, Mikityuk K
    ANNALS OF NUCLEAR ENERGY 85, 544-551 (2015).
    DOI: 10.1016/j.anucene.2015.06.007
  • 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) , (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).
  • Pyrite in contact with supercritical water: the desolation of steam Stirling Andras, Rozgonyi Tamas, Krack Matthias, Bernasconi Marco
    PHYSICAL CHEMISTRY CHEMICAL PHYSICS 17, 17375-17379 (2015).
    DOI: 10.1039/c5cp01146a
  • 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
  • SERPENT-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst Aufiero M, Fiorina C, Laureau A, Rubiolo P, Valtavirta V
    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).
  • 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).
  • Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems Nikitin E, Fridman E, Mikityuk K
    ANNALS OF NUCLEAR ENERGY 75, 492-497 (2015).
    DOI: 10.1016/j.anucene.2014.08.054
  • 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).
  • The European Project ESNII Plus Vasile A, Wahide C, Latge CH, Chauvin N, Baeten P, Schyns M, Frogheri M, Mansani L, Stainsby R, Mikityuk K, Forni M, Hozer Z
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe -- Part I: Uranium fuel cycle Lindley B A, Fiorina C, Gregg R, Franceschini F, Parks G T
    PROGRESS IN NUCLEAR ENERGY 85, 498 (2015).
    DOI: 10.1016/j.pnucene.2015.07.020
  • 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
  • Validation of the Serpent and TRACE codes using the SHRT-17 and SHRT-45R loss-of-flow tests performed in the EBR-II reactor Zhang Y, Mikityuk K
    ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
  • 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
Top

2014

  • A PROCEDURE FOR THE PRE-CONCEPTUAL DESIGN OF FAST REACTORS AND APPLICATION TO A GAS-COOLED SUB-CRITICAL TRANSMUTER Fiorina C, Mikityuk K, Krepel J
    ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 22, 30387 (2014).
  • A TIME-DEPENDENT SOLVER FOR COUPLED NEUTRON-TRANSPORT THERMAL-MECHANICS CALCULATIONS AND SIMULATION OF A GODIVA PROMPT-CRITICAL BURST Fiorina C, Aufiero M, Pelloni S, Mikityuk K
    ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 22, 30395 (2014).
  • A thermal modelling of displacement cascades in uranium dioxide Martin G, Garcia P, Sabathier C, Devynck F, Krack M, Maillard S
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS 327, 108-112 (2014).
    DOI: 10.1016/j.nimb.2013.09.043
  • A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and simulation of the Godiva promt-critical bursts Fiorina C, Aufiero M, Pelloni S, Mikityuk K
    ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 7-11 July 2014, ICONE22-30395 (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).
  • An innovative approach to dynamic modeling and simulation of the molten salt reactor experiment Zanetti M, Luzzi L, Cammi A, Fiorina C
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future , (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 an iterative methodology for cross-section and variance/covariance data adjustment to the analysis of fast spectrum systems accounting for non-linearity Pelloni Sandro
    ANNALS OF NUCLEAR ENERGY 72, 373-390 (2014).
    DOI: 10.1016/j.anucene.2014.06.002
  • 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).
  • Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking Lazaro A, Ammirabile L, Bandini G, Darmet G, Massara S, Dufour Ph, Tosello A, Gallego E, Jimenez G, Mikityuk K, Schikorr M, Bubelis E, Ponomarev A, Kruessmann R, Stempniewicz M
    NUCLEAR ENGINEERING AND DESIGN 266, 1-16 (2014).
    DOI: 10.1016/j.nucengdes.2013.10.019
  • Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis Lazaro A, Schikorr M, Mikityuk K, Ammirabile L, Bandini G, Darmet G, Schmitt D, Dufour Ph, Tosello A, Gallego E, Jimenez G, Bubelis E, Ponomarev A, Kruessmann R, Struwe D, Stempniewicz M
    NUCLEAR ENGINEERING AND DESIGN 277, 265-276 (2014).
    DOI: 10.1016/j.nucengdes.2014.02.029
  • 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).
  • Fuel cycle advantages and dynamics features of liquid fueled MSR Krepel Jiri, Hombourger Boris, Fiorina Carlo, Mikityuk Konstantin, Rohde Ulrich, Kliem Soeren, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 64, 380-397 (2014).
    DOI: 10.1016/j.anucene.2013.08.007
  • 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).
  • IAEA benchmark calculations on control rod withdrawal test performed during Phenix-End-Of-Life experiments -- benchmark results and comparison Pascal V, Prulhiere G, Vanier M, Fontaine B, Devan K, Chellapandi P, Kriventsev V, Monti S, Mikityuk K, Chenu A, Semenov M, Taiwo T, Takano K, Tiberi V
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future , (2014).
  • Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide Ngayam-Happy Raoul, Krack Matthias
    PROGRESS IN NUCLEAR ENERGY 72, 38-43 (2014).
    DOI: 10.1016/j.pnucene.2013.09.015
  • MOLTEN SALT FAST REACTOR BLANKET DESIGN AND PROLIFERATION RESISTANCE ASSESSMENT Bykov Valentyn, Krepel Jiri, Pautz Andreas
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5 , V005T17A061 (2014).
  • MOLTEN SALT REACTOR WITH SIMPLIFIED FUEL RECYCLING AND DELAYED CARRIER SALT CLEANING Krepel J, Hombourger B, Bykov V, Fiorina C, Mikityuk K, Pautz A
    ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 22, 30396 (2014).
  • Methodology assessment for the evaluation of the coolant void worth in sodium fast reactor with a low void effect core design Bortot S, Pelloni S, Mikityuk K
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future , (2014).
  • Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, Herman M, Ishikawa M, Ivanova T, Ivanov E, -J Kim S, Kodeli I, Manturov G, Mcknight R, Pelloni S, Perfetti C, J M Plompen A, T Rearden B, Rochman D, Sugino K, Trkov A, Wang W, Wu H, -S Yang W
    NUCLEAR DATA SHEETS 118, 38 (2014).
    DOI: 10.1016/j.nds.2014.04.005
  • 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).
  • Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulation Ngayam-Happy RA, Krack M
    SNA + MC 2013: Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo , 01301 (2014).
    DOI: 10.1051/snamc/201401301
  • 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).
  • Sensitivity and Uncertainty Analysis of the GFR MOX Fuel Subassembly Luley J, Vrban B, Cerba S, Hascik J, Necas V, Pelloni S
    NUCLEAR DATA SHEETS 118, 545 (2014).
    DOI: 10.1016/j.nds.2014.04.130
  • 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
  • The core design of ALFRED, a demonstrator for the European lead-cooled reactors Grasso G, Petrovich C, Mattioli D, Artioli C, Sciora P, Gugiu D, Bandini G, Bubelis E, Mikityuk K
    NUCLEAR ENGINEERING AND DESIGN 278, 287-301 (2014).
    DOI: 10.1016/j.nucengdes.2014.07.032
  • Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors A Lindley B, Fiorina C, Franceschini F, J Lahoda E, T Parks G
    PROGRESS IN NUCLEAR ENERGY 77, 107 (2014).
    DOI: 10.1016/j.pnucene.2014.06.010
  • 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).
  • Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
    Progress in Nuclear Science and Technology 4, 99 (2014).
    DOI: 10.15669/pnst.4.99
  • X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization Cozzo C, Orlov A, Borca C, Degueldre C
    PROGRESS IN NUCLEAR ENERGY 72, 91-95 (2014).
    DOI: 10.1016/j.pnucene.2013.09.009
Top

2013

  • A STATISTICAL SAMPLING METHOD FOR UNCERTAINTY ANALYSIS WITH SCALE AND XSUSA Williams M L, Ilas G, Jessee M A, Rearden B T, Wiarda D, Zwermann W, Gallner L, Klein M, Krzykacz-Hausmann B, Pautz A
    NUCLEAR TECHNOLOGY 183, 515-526 (2013).
  • A core design approach aimed at the sustainability and intrinsic safety of the European Lead-cooled Fast Reactor Grasso G, Doderlein C, Tucek K, Mikityuk K, Manni F, Gugiu D
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor Sun Kaichao, Krepel Jiri, Mikityuk Konstantin, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 53, 464-475 (2013).
    DOI: 10.1016/j.anucene.2012.10.004
  • A procedure for bypassing metastable states in local basis set DFT+U calculations and its application to uranium dioxide surfaces Rabone Jeremy, Krack Matthias
    COMPUTATIONAL MATERIALS SCIENCE 71, 157-164 (2013).
    DOI: 10.1016/j.commatsci.2013.01.023
  • ANALYSIS OF PIN REMOVAL EXPERIMENTS CONDUCTED IN A SUPERCRITICAL LIGHT WATER REACTOR-LIKE TEST LATTICE Chewla Rakesh, Raetz Dominik, Jordan Kelly A, Perret Gregory
    NUCLEAR TECHNOLOGY 183, 321-330 (2013).
  • Advantages and Dynamics Features of Liquid Fueled MSR Krepel J, Fiorina C, Kliem S
    CMSNT: Conference on Molten Salts in Nuclear Technology, January 9 -11, 2013, Bhabha Atomic Research Centre, Mumbai, India , (2013).
  • Analysis of Void Reactivity and Doppler Coefficient for Thorium- And Uranium-Fuelled Lead Fast Reactors Fiorina C, Cammi A, E Ricotti M, Krepel J, Mikityuk K
    ICAPP 2013: Proceedings of the International Congress on Advances in Nuclear Power Plants 2013 , (2013).
  • Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure Fiorina Carlo, Krepel Jiri, Cammi Antonio, Franceschini Fausto, Mikityuk Konstantin, Ricotti Marco Enrico
    ANNALS OF NUCLEAR ENERGY 53, 492-506 (2013).
    DOI: 10.1016/j.anucene.2012.09.004
  • Application of power time-projection on the operator-splitting coupling scheme of the trace/S3K coupled code Wicaksono D, Zerkak O, Nikitin K, Ferroukhi H, Chawla R
    M&C 2013 1, 1748 (2013).
  • Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface Khvostov G, Lyon W, Zimmermann M A
    ANNALS OF NUCLEAR ENERGY 62, 398-412 (2013).
    DOI: 10.1016/j.anucene.2013.07.002
  • Benchmark calculations on control rod withdrawal tests performed during PHENIX end-of-life experiments Pascal V, Prulhiere G, Fontaine B, Devan K, Kriventsev V, Monti S, Mikityuk K, Semenov M, Taiwo T, Takano K, Tiberi V
    ICAPP 2013: Proceedings of the International Congress on Advances in Nuclear Power Plants 2013 , (2013).
  • COUPLED 3-D NEUTRONICS/THERMAL-HYDRAULICS OPTIMIZATION STUDY FOR IMPROVING THE RESPONSE OF A 3600 MW(THERMAL) SFR CORE TO AN UNPROTECTED LOSS-OF-FLOW ACCIDENT Sun Kaichao, Chenu Aurelia, Krepel Jiri, Mikityuk Konstantin, Chawla Rakesh
    NUCLEAR TECHNOLOGY 183, 484-503 (2013).
  • Characterization method of dielectric properties of free falling drops in a microwave processing cavity and its application in microwave internal gelation Cabanes-Sempere M, Catala-Civera J M, Penaranda-Foix F L, Cozzo C, Vaucher S, Pouchon M A
    MEASUREMENT SCIENCE & TECHNOLOGY 24, 095009 (2013).
    DOI: 10.1088/0957-0233/24/9/095009
  • Comparison of serpent and CASMO-5M for pressurized water reactors models Hursin M, Vasiliev A, Ferroukhi H, Pautz A
    M&C 2013 1, 1565 (2013).
  • Demonstrating the effectiveness of the European LFR concept: the ALFRED core design Grasso G, Petrovic C, Mikityuk K, Mattioli D, Manni F, Gugiu D
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Dependence of the thorium closed fuel cycle parameters on the moderation level of the molten salt reactor Krepel J, Hombourger B, Mikityuk K
    ICAPP 2013: Proceedings of the International Congress on Advances in Nuclear Power Plants 2013 , (2013).
  • EFFECTS OF NUCLEAR DATA UNCERTAINTIES ON THE NEA/OECD PWR MOX/UO2 CORE ROD EJECTION BENCHMARK Pasichnyk Ihor, Klein Markus, Velkov Kiril, Zwermann Winfried, Pautz Andreas
    NUCLEAR TECHNOLOGY 183, 464-472 (2013).
  • ELECTRA-FORTE, a really small SMR for the Canadian market Wallenius J, Bortot S, Suvdanisetseg E
    2013 ANS Winter Meeting and Technology Expo, November 10-14, 2013, Washington, DC, USA , (2013).
  • ESFR core optimization and uncertainty studies Rineiski A, Vezzoni B, Zhang D, Marchetti M, Gabrielli F, Maschek W, -N Chen X, Buiron L, Krepel J, Sun K, Mikityuk K, Polidoro F, Rochman D, J Koning A, F DaCruz D, Tsige-Tamirat H, Sunderland R
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Experimental Validation of 3-D Reconstructed Pin Power Distributions in Full-Scale BWR Fuel Assemblies with Partial-Length Rods Giust Flavio Dante, Grimm Peter, Chawla Rakesh
    NUCLEAR SCIENCE AND ENGINEERING 175, 292-307 (2013).
  • FAST Code System: Review of Recent Applications Mikityuk K, Krepel J, Pelloni S, Girardin G, Chenu A, Sun K, Epiney A, Adams R, Ghasabyan L, Alonso M, Reiterer F
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Fast reactor physics Mikityuk K
    ThEC13: Thorium Energy Conference, October 27-31, 2013, CERN, Geneva, Switzerland , (2013).
  • First principle-based AKMC modelling of the formation and medium-term evolution of point defect and solute-rich clusters in a neutron irradiated complex Fe-CuMnNiSiP alloy representative of reactor pressure vessel steels Ngayam-Happy R, Becquart C S, Domain C
    JOURNAL OF NUCLEAR MATERIALS 440, 143-152 (2013).
    DOI: 10.1016/j.jnucmat.2013.04.081
  • Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor Kroehnert H, Perret G, Murphy M F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 698, 72-80 (2013).
    DOI: 10.1016/j.nima.2012.09.008
  • Gas Cooled Fast Reactors: Recent Advances and Prospects Poette C, Guedeney P, Stainsby R, Mikityuk K, Knol S
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident Hursin Mathieu, Downar Thomas J, Montgomery Robert
    NUCLEAR ENGINEERING AND DESIGN 262, 180-188 (2013).
    DOI: 10.1016/j.nucengdes.2013.04.023
  • Implementation and Validation of a Condensation heat Transfer Model for Slightly Inclined Horizontal Pipes for RELAP5 Szijarto R, Freixa J, Prasser H
    NURETH 15: Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 1 (2013).
  • International benchmark on the natural convection test in Phenix reactor Tenchine D, Pialla D, Fanning T H, Thomas J W, Chellapandi P, Shvetsov Y, Maas L, Jeong H -Y, Mikityuk K, Chenu A, Mochizuki H, Monti S
    NUCLEAR ENGINEERING AND DESIGN 258, 189-198 (2013).
    DOI: 10.1016/j.nucengdes.2013.02.010
  • Investigation of the Coupled Reactivity Effects of the Movable Reflector and Safety Control Rods in the GFR Vrban B, Cerba S, Luley J, Hascik J, Necas V, Pelloni S
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Investigation of the MSFR core physics and fuel cycle characteristics Fiorina Carlo, Aufiero Manuele, Cammi Antonio, Franceschini Fausto, Krepel Jiri, Luzzi Lelio, Mikityuk Konstantin, Ricotti Marco Enrico
    PROGRESS IN NUCLEAR ENERGY 68, 153-168 (2013).
    DOI: 10.1016/j.pnucene.2013.06.006
  • LFR safety approach and main ELFR safety analysis results Bubelis E, Schikorr M, Frogheri M, Mansani L, Bandini G, Burgazzi L, Mikityuk K, Zhang Y, Lo Frano R, Forgione N
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method Bosshard C, Dehbi A, Deville M, Leriche E, Puragliesi R, Soldati A
    COMPUTERS & FLUIDS 86, 210 (2013).
    DOI: 10.1016/j.compfluid.2013.07.007
  • MSFR TRU-burining potential and comparison with an SFR Fiorina C, Franceschini F, Cammi A, Krepel J
    GLOBAL 2013: International Nuclear Fuel Cycle Conference, Sept. 29 - Oct. 3, 2013, Salt Lake City, USA , (2013).
  • Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, Herman M, Ishikawa M, Ivanova T, Ivanov E, -J Kim S, Kodeli I, Manturov G, Mcknight R, Pelloni S, Perfetti C, Plompen A, T Rearden B, Rochman D, Sugino K, Trkov A, Wang W, Wu H, -S Yang W
    ND2013: International Conference on Nuclear Data for Science and Technology , (2013).
  • Modeling issues in small HLMC fast reactors: ELECTRA case study Bortot S, Wallenius J, Suvdanisetseg E
    2013 ANS Winter Meeting and Technology Expo, November 10-14, 2013, Washington, DC, USA , (2013).
  • New transient analysis of the Superphenix start-up tests Mikityuk K, Schikorr M
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H
    Science and Technology of Nuclear Installations , 549793 (2013).
    DOI: 10.1155/2013/549793
  • PSI studies on advanced fuel cycle options for fast/thermal MSR utilizing thorium Krepel J
    ThEC13: Thorium Energy Conference, October 27-31, 2013, CERN, Geneva, Switzerland , (2013).
  • Post-Analysis of a Turbine Trip Test at a BWR/6 using the TRACE/S3K Coupled Code Nikitin K, Gudmunsson T, Canepa S, Zerkak O, Ferroukhi H, Pautz A
    NURETH 15: Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 1 (2013).
  • Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation Freixa J, Kim T -W, Manera A
    NUCLEAR ENGINEERING AND DESIGN 264, 153-160 (2013).
    DOI: 10.1016/j.nucengdes.2013.02.023
  • Power and thermal study of a single drop heated while passing through a TE10p rectangular cavity Cabanes-Sempere M, Canos AJ, Catala-Civera JM, Penaranda-Foix FL, Cozzo C, Pouchon MA
    International Microwave Symposium (IMS 2013), Seattle, WA, USA , 1 (2013).
    DOI: 10.1109/MWSYM.2013.6697661
  • Reactivity effect of steam/water ingress in Generation-IV Gas-cooled Fast Reactor core Mikityuk K, Perko Z, Girardin G
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Reanalysis of the Gas-cooled fast reactor experiments at the zero power facility Proteus - Spectral indices Perret G, Pattupara R M, Girardin G, Chawla R
    WONDER-2012 - 3RD INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS 42, UNSP 05002 (2013).
    DOI: 10.1051/epjconf/20134205002
  • Safety analysis results of the DBC transients performed for the ALFRED reactor Bubelis E, Schikorr M, Mansani L, Bandini G, Mikityuk K, Zhang Y, Geffraye G
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters Krepel J, Brankov V, Mikityuk K
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
  • Sensitivity and Uncertainty Analysis of the GFR MOX Fuel Subassembly Luley J, Vrban B, Cerba S, Hascik J, Necas V, Pelloni S
    ND2013: International Conference on Nuclear Data for Science and Technology , (2013).
  • Simulation of International Standard Problem ISP-42 Phase B using In-House Coupled Code GOTHIC-TRACE Adamsson C, Papini D, Zerkak O, Prasser H
    NURETH 15: Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 1 (2013).
  • Simulation of International Standard Problem ISP-42 Phase B using the Containment Code GOTHIC Papini D, Adamsson C, Andreani M, Prasser H
    NURETH 15: Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 1 (2013).
  • TRANSITION TO CASMO-5M AND SIMULATE-3K FOR STABILITY ANALYSES OF THE SWISS BOILING WATER REACTORS Dokhane Abdelhamid, Canepa Stefano, Ferroukhi Hakim
    NUCLEAR TECHNOLOGY 183, 341-353 (2013).
  • The MSFR as a flexible CR reactor: the viewpoint of safety Fiorina C, Franceschini F, Cammi A, Krepel J
    GLOBAL 2013: International Nuclear Fuel Cycle Conference, Sept. 29 - Oct. 3, 2013, Salt Lake City, USA , (2013).
  • The proto-Earth geo-reactor: a thorium reactor? Degueldre C, Fiorina C
    ThEC13: Thorium Energy Conference, October 27-31, 2013, CERN, Geneva, Switzerland , (2013).
  • Thermal-Hydraulic System Code Performance for SBLOCA Phenomonelogy using Different geometries and Scales Freixa J, Belaid S, Zerkak O
    NURETH 15: Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 1 (2013).
  • Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor Fiorina C, Cammi A, Luzzi L, Mikityuk K, Ninokata H, E Ricotti M
    31st UIT Heat Transfer Conference, June 25-27, 2013, Como, Italy , (2013).
  • Use of SERPENT Monte-Carlo code for development of 3D full-core models of Gen-IV fast spectrum reactors and preparation of safety parameters/cross-section data for transient analysis Ghasabyan L, Mikityuk K, Krepel J, Pelloni S
    FR13: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, March 4-7, 2013, Paris, France. , (2013).
Top

2012

  • A novel design approach for a neutron measurement station for burnt fuel Dietler Rodolfo, Hursin Mathieu, Perret Gregory, Jordan Kelly, Chawla Rakesh
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 693, 59-66 (2012).
    DOI: 10.1016/j.nima.2012.07.009
  • A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions Epiney A, Alpy N, Mikityuk K, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 242, 267-284 (2012).
    DOI: 10.1016/j.nucengdes.2011.10.011
  • ANALYSIS OF PIN REMOVAL EXPERIMENTS CONDUCTED IN AN SCWR-LIKE TEST LATTICE Chawla R, Raetz D, Jordan KA, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 283_1 (2012).
  • ANALYSIS OF THE ISP-50 DIRECT VESSEL INJECTION SBLOCA IN THE ATLAS FACILITY WITH THE RELAP5/MOD3.3 CODE Sharabi Medhat, Freixa Jordi
    Nuclear Engineering and Technology 44, 709-718 (2012).
    DOI: 10.5516/NET.02.2012.712
  • Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes Kim Taewan, Petrov Victor, Manera Annalisa, Lo Simon
    Science and Technology of Nuclear Installations , 746467 (2012).
    DOI: 10.1155/2012/746467
  • Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments Chenu A, Adams R, Mikityuk K, Chawla R
    ANNALS OF NUCLEAR ENERGY 49, 182-190 (2012).
    DOI: 10.1016/j.anucene.2012.05.036
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