Full LRS Publication List

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).
  • 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, 004 (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
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 A, 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
  • Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test Chenu A, Mikityuk K, Chawla R
    ANNALS OF NUCLEAR ENERGY 49, 191-199 (2012).
    DOI: 10.1016/j.anucene.2012.05.035
  • Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX Marinoni Alessandro, Girardin Gaetan, Mikityuk Konstantin
    ANNALS OF NUCLEAR ENERGY 44, 26-33 (2012).
    DOI: 10.1016/j.anucene.2012.01.011
  • Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code Hursin Mathieu, Downar Thomas J, Kochunas Brendan
    NUCLEAR SCIENCE AND ENGINEERING 170, 151-167 (2012).
  • Atomistic Simulation of Nuclear Fuels Krack M
    Materials Research Society Symposium - Proceedings 1383, mrsf11-1383-a03-11 (2012).
    DOI: 10.1557/opl.2012.520
  • Comparison of open and closed U-Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure Krepel Jiri, Pelloni Sandro, Mikityuk Konstantin
    NUCLEAR ENGINEERING AND DESIGN 250, 392-402 (2012).
    DOI: 10.1016/j.nucengdes.2012.06.004
  • Coupled 3D-Neutronics / Thermal-Hydraulics Analysis of an Unprotected Loss-of-Flow Accident for a 3600 MWth SFR Core Sun K, Chenu A, Mikityuk K, Krepel J, Chawla R
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 285_1 (2012).
  • DESIGN OF A PROTEUS LATTICE REPRESENTATIVE OF A BURNT AND FRESH FUEL INTERFACE AT POWER CONDITIONS IN LIGHT WATER REACTORS Hursin M, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 52_1 (2012).
  • EXPERIMENTAL VALIDATION OF 3D RECONSTRUCTED PIN-POWER DISTRIBUTIONS IN FULL-SCALE BWR FUEL ASSEMBLIES WITH PARTIAL LENGTH RODS Giust FD, Grimm P, Chawla R
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 295_1 (2012).
  • EXPERIMENTAL VALIDATION OF CASMO-4E AND CASMO-5M FOR RADIAL FISSION RATE DISTRIBUTIONS IN A WESTINGHOUSE SVEA-96 OPTIMA2 BWR FUEL ASSEMBLY Grimm P, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 50_1 (2012).
  • Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice Raetz Dominik, Jordan Kelly A, Bayard Andre-Samuel P, Perret Gregory, Chawla Rakesh
    NUCLEAR ENGINEERING AND DESIGN 247, 236-247 (2012).
    DOI: 10.1016/j.nucengdes.2012.02.011
  • Frenkel pair recombinations in UO2: Importance of explicit description of polarizability in core-shell molecular dynamics simulations Devynck Fabien, Iannuzzi Marcella, Krack Matthias
    PHYSICAL REVIEW B 85, 184103 (2012).
    DOI: 10.1103/PhysRevB.85.184103
  • NUCLEAR DATA UNCERTAINTY ANALYSIS FOR THE GENERATION IV GAS-COOLED FAST REACTOR Pelloni S, Mikityuk K
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 125_1 (2012).
  • NUCLEAR DATA UNCERTAINTY PROPAGATION IN A LATTICE PHYSICS CODE USING STOCHASTIC SAMPLING Wieselquist W, Vasiliev A, Ferroukhi H
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 284_1 (2012).
  • On the Combination of Delayed Neutron and Delayed Gamma Measurement Techniques for Nuclear Fuel and Its Application to Nuclear Data Uncertainty Reduction Perret Gregory, Jordan Kelly A
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE 59, 3166-3172 (2012).
    DOI: 10.1109/TNS.2012.2215339
  • Quantitative evaluation of change in core damage frequency by postulated power uprate: Medium-break loss-of-coolant-accidents Kim T W, Dang V N, Zimmermann M A, Manera A
    ANNALS OF NUCLEAR ENERGY 47, 69-80 (2012).
    DOI: 10.1016/j.anucene.2012.04.021
  • REACTOR PHYSICS STUDIES FOR ASSESSMENT OF TRAMP URANIUM METHODS Grimm P, Vasiliev A, Wieselquist W, Ferroukhi H
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 51_1 (2012).
  • REANALYSIS OF THE GAS-COOLED FAST REACTOR EXPERIMENTS AT THE ZERO POWER FACILITY PROTEUS – SPECTRAL INDICES Perret G, Pattupara RM, Girardin G, Chawla R
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 176_1 (2012).
  • Remarks on Consistent Development of Plant Nodalizations: An Example of Application to the ROSA Integral Test Facility Freixa J, Manera A
    Science and Technology of Nuclear Installations , 158617 (2012).
    DOI: 10.1155/2012/158617
  • STOCHASTIC SAMPLING METHOD WITH MCNPX FOR NUCLEAR DATA UNCERTAINTY PROPAGATION IN CRITICALITY SAFETY APPLICATIONS Zhu T, Vasiliev A, Wieselquist W, Ferroukhi H
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 287_1 (2012).
  • Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE Aounallah Y
    KERNTECHNIK 77, 316-323 (2012).
    DOI: 10.3139/124.110214
  • TOWARDS A REFERENCE NUMERICAL SCHEME USING MCNPX FOR PWR CONTROL ROD TIP FLUENCE ESTIMATIONS Ferroukhi H, Vasiliev A, Dufresne A, Chawla R
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 309_1 (2012).
  • TOWARDS THE REANALYSIS OF VOID COEFFICIENTS MEASUREMENTS AT PROTEUS FOR HIGH CONVERSION LIGHT WATER REACTOR LATTICES Hursin M, Koeberl O, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 53_1 (2012).
  • Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation Freixa Jordi, Kim Tae-Wan, Manera Annalisa
    NUCLEAR ENGINEERING AND DESIGN 249, 97-103 (2012).
    DOI: 10.1016/j.nucengdes.2011.08.061
  • Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs Dokhane A, Canepa S, Ferroukhi H
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 311_1 (2012).
  • Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility Kozmenkov Y, Rohde U, Manera A
    NUCLEAR ENGINEERING AND DESIGN 243, 168-175 (2012).
    DOI: 10.1016/j.nucengdes.2011.10.053
Top

2011

  • A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel Jordan K A, Perret G
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 634, 91-100 (2011).
    DOI: 10.1016/j.nima.2011.01.064
  • A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code Khvostov G, Mikityuk K, Zimmermann M A
    NUCLEAR ENGINEERING AND DESIGN 241, 2983-3007 (2011).
    DOI: 10.1016/j.nucengdes.2011.06.020
  • A new cross-section generation model in the FAST code system and its application to gas-and sodium-cooled Generation IV fast reactors Pelloni Sandro, Mikityuk Konstantin
    ANNALS OF NUCLEAR ENERGY 38, 1-13 (2011).
    DOI: 10.1016/j.anucene.2010.08.009
  • Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code Nikitin Konstantin, Manera Annalisa
    NUCLEAR ENGINEERING AND DESIGN 241, 2240-2247 (2011).
    DOI: 10.1016/j.nucengdes.2011.03.021
  • Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project Herranz L E, Vallejo I, Khvostov G, Sercombe J, Zhou G
    NUCLEAR ENGINEERING AND DESIGN 241, 815-825 (2011).
    DOI: 10.1016/j.nucengdes.2011.01.007
  • Assessment of the JEFF-3.1.1 Neutron Data Library for CSE of LWR Fuel Storage Pools Kolbe Edwin, Vasiliev Alexander, Ferroukhi Hakim
    JOURNAL OF THE KOREAN PHYSICAL SOCIETY 59, 1174-1178 (2011).
    DOI: 10.3938/jkps.59.1174
  • Comparison of Neutron Data Libraries for the Analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX Code Vasiliev A, Kolbe E, Ferroukhi H, Pittarello R
    JOURNAL OF THE KOREAN PHYSICAL SOCIETY 59, 2047-2050 (2011).
    DOI: 10.3938/jkps.59.2047
  • Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice Raetz Dominik, Jordan Kelly A, Murphy Michael F, Perret Gregory, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 794-801 (2011).
    DOI: 10.1016/j.anucene.2010.11.021
  • DNS of buoyancy-driven flows and Lagrangian particle tracking in a square cavity at high Rayleigh numbers Puragliesi R, Dehbi A, Leriche E, Soldati A, Deville M O
    INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW 32, 915-931 (2011).
    DOI: 10.1016/j.ijheatfluidflow.2011.06.007
  • Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR (TM): CFD investigations and comparison with experimental results Petrov Victor, Manera Annalisa
    NUCLEAR ENGINEERING AND DESIGN 241, 1478-1485 (2011).
    DOI: 10.1016/j.nucengdes.2011.02.027
  • Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies Giust Flavio D, Grimm Peter, Chawla Rakesh
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME 133, 052909 (2011).
    DOI: 10.1115/1.4002823
  • Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice Raetz Dominik, Jordan Kelly A, Perret Gregory, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 2319-2332 (2011).
    DOI: 10.1016/j.anucene.2011.07.007
  • FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests Mikityuk K, Shestopalov A
    NUCLEAR ENGINEERING AND DESIGN 241, 2455-2461 (2011).
    DOI: 10.1016/j.nucengdes.2011.04.033
  • First-principles study of nitrogen doping in cubic and amorphous Ge2Sb2Te5 Caravati S, Colleoni D, Mazzarello R, Kuehne T D, Krack M, Bernasconi M, Parrinello M
    JOURNAL OF PHYSICS-CONDENSED MATTER 23, 265801 (2011).
    DOI: 10.1088/0953-8984/23/26/265801
  • Gas cooled fast reactor research in Europe Stainsby Richard, Peers Karen, Mitchell Colin, Poette Christian, Mikityuk Konstantin, Somers Joe
    NUCLEAR ENGINEERING AND DESIGN 241, 3481-3489 (2011).
    DOI: 10.1016/j.nucengdes.2011.08.005
  • Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm Bertolotto D, Manera A, Macian-Juan R, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 241, 245-256 (2011).
    DOI: 10.1016/j.nucengdes.2010.10.021
  • Investigation of the void reactivity effect in large-size Lead Fast Reactors Bortot Sara, Artioli Carlo
    ANNALS OF NUCLEAR ENERGY 38, 1004-1013 (2011).
    DOI: 10.1016/j.anucene.2011.01.017
  • NURESIM - A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis Chauliac Christian, Aragones Jose-Maria, Bestion Dominique, Cacuci Dan Gabriel, Crouzet Nicolas, Weiss Frank-Peter, Zimmermann Martin A
    NUCLEAR ENGINEERING AND DESIGN 241, 3416-3426 (2011).
    DOI: 10.1016/j.nucengdes.2010.09.040
  • Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow Chenu A, Mikityuk K, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 241, 3898-3909 (2011).
    DOI: 10.1016/j.nucengdes.2011.07.009
  • Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip Vinai Paolo, Macian-Juan Rafael, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 358-370 (2011).
    DOI: 10.1016/j.anucene.2010.10.007
  • Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark Pittarello R, Vasiliev A, Ferroukhi H, Chawla R
    ANNALS OF NUCLEAR ENERGY 38, 1842-1851 (2011).
    DOI: 10.1016/j.anucene.2011.05.017
  • Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code Khvostov G, Wiesenack W, Zimmermann M A, Ledergerber G
    NUCLEAR ENGINEERING AND DESIGN 241, 1500-1507 (2011).
    DOI: 10.1016/j.nucengdes.2011.03.003
  • Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme Perez M, Reventos F, Batet L, Guba A, Toth I, Mieusset T, Bazin P, de Crecy A, Borisov S, Skorek T, Glaeser H, Joucla J, Probst P, Ui A, Chung B D, Oh D Y, Pernica R, Kyncl M, Macek J, Manera A, Freixa J, Petruzzi A, D'Auria F, Del Nevo A
    NUCLEAR ENGINEERING AND DESIGN 241, 4206-4222 (2011).
    DOI: 10.1016/j.nucengdes.2011.08.019
  • Verification of a TRACE EPR (TM) model on the basis of a scaling calculation of an SBLOCA ROSA test Freixa J, Manera A
    NUCLEAR ENGINEERING AND DESIGN 241, 888-896 (2011).
    DOI: 10.1016/j.nucengdes.2010.12.016
  • Vessel coolant mixing effects on a PWR Main Steam Line Break transient Zerkak Omar, Ferroukhi Hakim
    ANNALS OF NUCLEAR ENERGY 38, 60-71 (2011).
    DOI: 10.1016/j.anucene.2010.08.016
  • Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle Sun Kaichao, Krepel Jiri, Mikityuk Konstantin, Pelloni Sandro, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 1645-1657 (2011).
    DOI: 10.1016/j.anucene.2011.02.018
Top

2010

  • Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE Freixa J, Manera A
    NUCLEAR ENGINEERING AND DESIGN 240, 1779-1788 (2010).
    DOI: 10.1016/j.nucengdes.2010.02.007
  • Analytical model of the oxide layer build-up in complex lead-cooled systems Mikityuk K
    NUCLEAR ENGINEERING AND DESIGN 240, 3632-3637 (2010).
    DOI: 10.1016/j.nucengdes.2010.07.005
  • Development of a Wide-Range Pre-CHF Convective Boiling Correlation Aounallah Yacine
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 47, 357-366 (2010).
    DOI: 10.3327/jnst.47.357
  • FAST Code System: Review of Recent Developments and Near-Future Plans Mikityuk Konstantin, Krepel Jiri, Pelloni Sandro, Chenu Aurelia, Petkevich Petr, Chawla Rakesh
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME 132, 102915 (2010).
    DOI: 10.1115/1.4000336
  • First principles study of crystalline and amorphous Ge2Sb2Te5 and the effects of stoichiometric defects (vol 21, 255501, 2009) Caravati S, Bernasconi M, Kuehne T D, Krack M, Parrinello M
    JOURNAL OF PHYSICS-CONDENSED MATTER 22, 399801 (2010).
    DOI: 10.1088/0953-8984/22/39/399801
  • Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel Krohnert H, Perret G, Murphy M F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 624, 101-108 (2010).
    DOI: 10.1016/j.nima.2010.09.033
  • GFR equilibrium cycle analysis with the EQL3D procedure Krepel Jiri, Pelloni Sandro, Mikityuk Konstantin, Coddington Paul
    NUCLEAR ENGINEERING AND DESIGN 240, 905-917 (2010).
    DOI: 10.1016/j.nucengdes.2009.12.007
  • Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions Epiney Aaron, Mikityuk Konstantin, Chawla Rakesh
    NUCLEAR ENGINEERING AND DESIGN 240, 3115-3125 (2010).
    DOI: 10.1016/j.nucengdes.2010.05.030
  • Investigating the ESBWR stability with experimental and numerical tools: A comparative study Rohde M, Marcel C P, Manera A, Van der Hagen T H J J, Shiralkar B
    NUCLEAR ENGINEERING AND DESIGN 240, 375-384 (2010).
    DOI: 10.1016/j.nucengdes.2008.01.016
  • Main Results of Phase IV BEMUSE Project: Simulation of LBLOCA in an NPP Perez M, Reventos F, Batet L, Pericas R, Toth I, Bazin P, de Crecy A, Germain P, Borisov S, Glaeser H, Skorek T, Joucla J, Probst P, Ui A, Chung B, Oh D Y, Kyncl M, Pernica R, Manera A, D'Auria F, Petruzzi A, Del Nevo A
    Science and Technology of Nuclear Installations , 219294 (2010).
    DOI: 10.1155/2010/219294
  • Performance of a Monte-Carlo solution for the HB Robinson-2 Pressure Vessel Dosimetry Benchmark Vasiliev A, Ferroukhi H, Kolbe E
    ANNALS OF NUCLEAR ENERGY 37, 1404-1410 (2010).
    DOI: 10.1016/j.anucene.2010.05.019
  • Probing the Mechanical Properties of Hybrid Inorganic-Organic Frameworks: A Computational and Experimental Study Kosa Monica, Tan Jin-Chong, Merrill Crystal A, Krack Matthias, Cheetham Anthony K, Parrinello Michele
    CHEMPHYSCHEM 11, 2332-2336 (2010).
    DOI: 10.1002/cphc.201000362
  • TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods Epiney Aaron, Mikityuk Konstantin, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 37, 875-887 (2010).
    DOI: 10.1016/j.anucene.2010.01.020
  • The effect of modern thermal neutron scattering sublibraries on criticality safety evaluations of wet storage pools Kolbe Edwin, Vasiliev Alexander, Ferroukhi Hakim
    ANNALS OF NUCLEAR ENERGY 37, 371-379 (2010).
    DOI: 10.1016/j.anucene.2009.12.003
Top

2009

  • Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters Manera A, Ozar B, Paranjape S, Ishii M, Prasser H -M
    NUCLEAR ENGINEERING AND DESIGN 239, 1718-1724 (2009).
    DOI: 10.1016/j.nucengdes.2008.06.015
  • Cross-section modelling effects on pressurised water reactor main steam line break analyses Ferroukhi Hakim, Zerkak Omar, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 36, 1184-1200 (2009).
    DOI: 10.1016/j.anucene.2009.04.006
  • Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography Caruso S, Murphy M F, Jatuff F, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 239, 1220-1228 (2009).
    DOI: 10.1016/j.nucengdes.2009.02.019
  • Development and benchmarking of a mechanical model for GFR plate-type fuel Petkevich Petr, Mikityuk Konstantin, Coddington Paul, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 36, 1262-1269 (2009).
    DOI: 10.1016/j.anucene.2009.01.015
  • EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors Krepel Jiri, Pelloni Sandro, Mikityuk Konstantin, Coddington Paul
    ANNALS OF NUCLEAR ENERGY 36, 550-561 (2009).
    DOI: 10.1016/j.anucene.2009.01.008
  • Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme Ferroukhi H, Hollard J -M, Zimmermann M A, Chawla R
    ANNALS OF NUCLEAR ENERGY 36, 286-291 (2009).
    DOI: 10.1016/j.anucene.2008.12.010
  • Experimental Validation of Reaction Rate Distributions for a SVEA-96+BWR Assembly with Hafnium Control Blades Plaschy Michael, Murphy Michael, Jatuff Fabian, Luethi Anton, Grimm Peter, Jacot-Guillarmod Roland, Giust Flavio, Bergmann Uffe, Helmersson Sture, Seiler Rudolf, Krouthen Jan, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 46, 933-943 (2009).
    DOI: 10.1080/18811248.2009.9711602
  • First principles study of crystalline and amorphous Ge2Sb2Te5 and the effects of stoichiometric defects (vol 21, 255501, 2009) Caravati S, Bernasconi M, Kuehne T D, Krack M, Parrinello M
    JOURNAL OF PHYSICS-CONDENSED MATTER 21, 499803 (2009).
    DOI: 10.1088/0953-8984/21/49/499803
  • First-principles study of crystalline and amorphous Ge(2)Sb(2)Te(5) and the effects of stoichiometric defects Caravati S, Bernasconi M, Kuehne T D, Krack M, Parrinello M
    JOURNAL OF PHYSICS-CONDENSED MATTER 21, 255501 (2009).
    DOI: 10.1088/0953-8984/21/25/255501
  • Fuel performance analysis for PWR cores Romano Antonino, Shuffler Carter A, Garkisch Hans D, Olander Donald R, Todreas Neil E
    NUCLEAR ENGINEERING AND DESIGN 239, 1481-1488 (2009).
    DOI: 10.1016/j.nucengdes.2008.11.022
  • Gas Cooled Fast Reactor Research and Development in the European Union Stainsby Richard, Peers Karen, Mitchell Colin, Poette Christian, Mikityuk Konstantin, Somers Joe
    Science and Technology of Nuclear Installations , 238624 (2009).
    DOI: 10.1155/2009/238624
  • Heat transfer to liquid metal: Review of data and correlations for tube bundles Mikityuk Konstantin
    NUCLEAR ENGINEERING AND DESIGN 239, 680-687 (2009).
    DOI: 10.1016/j.nucengdes.2008.12.014
  • Impact of New Gadolinium Cross Sections on Reaction Rate Distributions in 10 x 10 BWR Assemblies Perret G, Murphy M F, Jatuff F, Sublet J-Ch, Bouland O, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 163, 17-25 (2009).
  • Interfacial water: A first principles molecular dynamics study of a nanoscale water film on salt Liu Li-Min, Krack Matthias, Michaelides Angelos
    JOURNAL OF CHEMICAL PHYSICS 130, 234702 (2009).
    DOI: 10.1063/1.3152845
  • PHYSOR 2008 Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 36, 255-257 (2009).
    DOI: 10.1016/j.anucene.2008.11.008
  • Static and Dynamical Properties of Liquid Water from First Principles by a Novel Car-Parrinello-like Approach Kuehne Thomas D, Krack Matthias, Parrinello Michele
    JOURNAL OF CHEMICAL THEORY AND COMPUTATION 5, 235-241 (2009).
    DOI: 10.1021/ct800417q
  • Study of the PWR REA pulse width for realistic UO2 and MOX core designs using 3D kinetics methods Ferroukhi Hakim, Zimmermann Martin A
    ANNALS OF NUCLEAR ENERGY 36, 1170-1183 (2009).
    DOI: 10.1016/j.anucene.2009.04.007
  • Superionic Conduction in Substoichiometric LiAl Alloy: An Ab Initio Study Cucinotta Clotilde S, Miceli Giacomo, Raiteri Paolo, Krack Matthias, Kuehne Thomas D, Bernasconi Marco, Parrinello Michele
    PHYSICAL REVIEW LETTERS 103, 125901 (2009).
    DOI: 10.1103/PhysRevLett.103.125901
  • THREE-DIMENSIONAL CORE BEHAVIOUR ANALYSIS OF THE GAS-COOLED FAST REACTOR (GFR) DURING HYPOTHETICAL CONTROL ASSEMBLY WITHDRAWAL ACCIDENTS Girardin Gaetan, Blanchet David, Mikityuk Konstantin, Rimpault Gerald, Chawla Rakesh
    ICONE 17: Proceedings of the 17th International Conference on Nuclear Engineering, Vol. 1, , 881-892 (2009).
  • TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions Chenu A, Mikityuk K, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 239, 2417-2429 (2009).
    DOI: 10.1016/j.nucengdes.2009.07.015
  • Unravelling the Mechanism of Pressure Induced Amorphization of Phase Change Materials Caravati S, Bernasconi M, Kuehne T D, Krack M, Parrinello M
    PHYSICAL REVIEW LETTERS 102, 205502 (2009).
    DOI: 10.1103/PhysRevLett.102.205502
  • Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model Plaschy M, Murphy M, Jatuff F, Perret G, Seiler R, Chawla R
    ANNALS OF NUCLEAR ENERGY 36, 1536 (2009).
    DOI: 10.1016/j.anucene.2009.07.012
  • Void reactivity coefficient benchmark results for a 10 x 10 BWR assembly in the full 0-100% void fraction range Jatuff F, Perret G, Murphy M F, Giust F, Chawla R
    ANNALS OF NUCLEAR ENERGY 36, 853-858 (2009).
    DOI: 10.1016/j.anucene.2009.02.013
Top

2008

  • A separate-effect-based new appraisal of convective boiling and its suppression Aounallah Yacine
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 45, 149-159 (2008).
    DOI: 10.3327/jnst.45.149
  • Analysis of radioactivity releases in the MEGAPIE reference accident Mikityuk Konstantin, Coddington Paul, Groeschel Friedrich
    NUCLEAR ENGINEERING AND DESIGN 238, 1838-1844 (2008).
    DOI: 10.1016/j.nucengdes.2007.12.004
  • Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5 Barten Werner, Jasiulevicius Audrius, Manera Annallsa, Macian-Juan Rafael, Zerkak Omar
    NUCLEAR ENGINEERING AND DESIGN 238, 1129-1145 (2008).
    DOI: 10.1016/j.nucengdes.2007.10.004
  • Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optimal assembly Perret G, Plaschy M, Murphy M F, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 478-484 (2008).
    DOI: 10.1016/j.anucene.2007.06.025
  • Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions Murphy M F, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 2042-2050 (2008).
    DOI: 10.1016/j.anucene.2008.06.001
  • Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of (CS)-C-134 Cs-137 and Eu-154 single ratios inhighly burnt UO2 Caruso S, Guenther-Leopold I, Murphy M F, Jatuff F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 589, 425-435 (2008).
    DOI: 10.1016/j.nima.2008.03.005
  • Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems Kolbe Edwin, Vasiliev Alexander, Ferroukhi Hakim, Zimmermann Martin A
    ANNALS OF NUCLEAR ENERGY 35, 1831-1841 (2008).
    DOI: 10.1016/j.anucene.2008.04.009
  • Density oscillations in a nanoscale water film on salt: Insight from ab initio molecular dynamics Liu Limin, Krack Matthias, Michaelides Angelos
    JOURNAL OF THE AMERICAN CHEMICAL SOCIETY 130, 8572-+ (2008).
    DOI: 10.1021/ja8014296
  • Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Serviere H, Fougeras P, Chaussonnet P, Domergue C, Laurens J -M, Philibert H
    REACTOR DOSIMETRY: 12TH INTERNATIONAL SYMPOSIUM 1490, 55-65 (2008).
  • Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor Girardin G, Rimpauit G, Morin F, Bosq J C, Coddington P, Mikityuk K, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 2206-2218 (2008).
    DOI: 10.1016/j.anucene.2008.09.008
  • Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+test lattice Chawla R, Jatuff F, Tani F
    ANNALS OF NUCLEAR ENERGY 35, 495-502 (2008).
    DOI: 10.1016/j.anucene.2007.06.027
  • Dynamics of molten salt reactors Krepel Jiri, Rohde Ulrich, Grundmann Ulrich, Weiss Frank-Peter
    NUCLEAR TECHNOLOGY 164, 34-44 (2008).
  • Interpretation of high-burnup fuel annealing tests Blair Paul, Khvostov Grigori, Romano Antonino, Hellwig Christian, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 45, 639-646 (2008).
    DOI: 10.3327/jnst.45.639
  • Management of actinide waste inventories in nuclear phase-out scenarios Cometto M, Wydler P, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 1447-1460 (2008).
    DOI: 10.1016/j.anucene.2008.01.016
  • Modeling the Hydrogen Storage Materials with Exposed M2+ Coordination Sites Kosa Monica, Krack Matthias, Cheetham Anthony K, Parrinello Michele
    JOURNAL OF PHYSICAL CHEMISTRY C 112, 16171-16173 (2008).
    DOI: 10.1021/jp806394g
  • Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography Caruso Stefano, Murphy Michael F, Jatuff Fabian, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 45, 828-835 (2008).
    DOI: 10.3327/jnst.45.828
  • On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test Vasiliev Alexander, Ferroukhi Hakim, Zimmermann Martin A, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 35, 565-569 (2008).
    DOI: 10.1016/j.anucene.2007.08.018
  • On the observation of discrepancies in the (16)O(n,alpha) data between different evaluated nuclear data files Vasiliev A, Ferroukhi H, Zimmermann M A, Kolbe E
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 2, PROCEEDINGS , 965-968 (2008).
    DOI: 10.1051/ndata:07445
  • On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations Vasiliev Alexander, Kolbe Edwin, Ferroukhi Hakim, Zimmermann Martin A, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 35, 2432-2435 (2008).
    DOI: 10.1016/j.anucene.2008.07.009
  • One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE Barten Werner, Manera Annalisa, Macian-Juan Rafael
    NUCLEAR ENGINEERING AND DESIGN 238, 2568-2582 (2008).
    DOI: 10.1016/j.nucengdes.2008.05.004
  • Towards the development of upper subcriticality limits on the basis of benchmark criticality calculations Vasiliev Alexander, Kolbe Edwin, Zimmermann Martin A
    ANNALS OF NUCLEAR ENERGY 35, 1764-1773 (2008).
    DOI: 10.1016/j.anucene.2008.01.017
  • Validation of standard neutron data libraries for LWR storage pools and transport casks criticality safety evaluations Kolbe Edwin, Vasiliev Alexander, Zimmermann Martin A
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 2, PROCEEDINGS , 799-802 (2008).
    DOI: 10.1051/ndata:07441
  • Verification of the TRACE code against the MEGAPIE transient data Bubelis Evaldas, Coddington Paul, Mikityuk Konstantin
    ANNALS OF NUCLEAR ENERGY 35, 1284-1295 (2008).
    DOI: 10.1016/j.anucene.2007.12.006
Top

2007

  • A statistical methodology for quantification of uncertainty in best estimate code physical models Vinai Paolo, Macian-Juan Rafael, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 34, 628-640 (2007).
    DOI: 10.1016/j.anucene.2007.03.003
  • Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients Zerkak Omar, Coddington Paul, Eitschberger Horst
    NUCLEAR ENGINEERING AND DESIGN 237, 1195-1208 (2007).
    DOI: 10.1016/j.nucengdes.2007.01.011
  • BWR stability and bifurcation analysis using reduced order models and system codes: Identification of a subcritical Hopf bifurcation using RAMONA Dokhane Abdelhamid, Hennig Dieter, Rizwan-uddin, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 34, 792-802 (2007).
    DOI: 10.1016/j.anucene.2007.04.003
  • Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems Mikityuk K, Coddington P, Pelloni S, Bubelis E, Chawla R
    NUCLEAR TECHNOLOGY 157, 18-36 (2007).
  • Development and benchmarking of a 2D model for GFR plate-type transient thermal fuel Petkevich Petr, Mikityuk Konstantin, Coddington Paul, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 34, 707-718 (2007).
    DOI: 10.1016/j.anucene.2007.03.009
  • Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data Vasiliev Alexander, Ferroukhi Hakim, Zimmermann Martin A, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 34, 615-627 (2007).
    DOI: 10.1016/j.anucene.2007.02.020
  • Evolution of porosity in the high-burnup fuel structure Romano Antonino, Horvath Matthias I, Restani Renato
    JOURNAL OF NUCLEAR MATERIALS 361, 62-68 (2007).
    DOI: 10.1016/j.jnucmat.2006.09.016
  • Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis Dokhane Abdelhamid, Hennig Dieter, Rizwan-uddin, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 34, 271-287 (2007).
    DOI: 10.1016/j.anucene.2006.12.005
  • Investigations of U-238 captures to total fissions in a Westinghouse SVEA-96+ assembly Bergmann U C, Grimm P, Jatuff F, Murphy M F, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 156, 86-95 (2007).
  • Radial and azimuthal U-235 fission and U-238 capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja O P, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 155, 96-101 (2007).
  • Statistical uncertainty analysis applied to fuel depletion calculations Macian Rafael, Zimmermann Martin A, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 44, 875-885 (2007).
    DOI: 10.3327/jnst.44.875
  • Validation of Cs-134, Cs-137 and Eu-154 single ratios as burnup monitors for ultra-high burnup UO2 fuel Caruso S, Murphy M, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 34, 28-35 (2007).
    DOI: 10.1016/j.anucene.2006.11.009
Top

2006

  • A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor Paratte J M, Frueh R, Kasemeyer U, Kalugin M A, Timm W, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 739-748 (2006).
    DOI: 10.1016/j.anucene.2005.09.012
  • Absolute depth-dose-rate measurements for an Ir-192 HDR brachytherapy source in water using MOSFET detectors Zilio Valery Olivier, Joneja Om Parkash, Popowski Youri, Rosenfeld Anatoly, Chawla Rakesh
    MEDICAL PHYSICS 33, 1532-1539 (2006).
    DOI: 10.1118/1.2198168
  • Advanced foil activation techniques for the measurement of within-pin distributions of the Cu-63(n,gamma)Cu-64 reaction rate in nuclear fuel Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 562, 393-400 (2006).
    DOI: 10.1016/j.nima.2006.03.004
  • Atomistic simulation of rapid compression of fractured silicon carbide Romano A, Li J, Yip S
    JOURNAL OF NUCLEAR MATERIALS 352, 22-28 (2006).
    DOI: 10.1016/j.jnucmat.2006.02.038
  • Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast Pelloni S, Bubelis E, Mikityuk K, Coddington P
    ANNALS OF NUCLEAR ENERGY 33, 499-509 (2006).
    DOI: 10.1016/j.anucene.2006.01.002
  • Calculations on fission gas behaviour in the high burnup structure Blair P, Romano A, HellWig C, Chawla R
    JOURNAL OF NUCLEAR MATERIALS 350, 232-239 (2006).
    DOI: 10.1016/j.jnucmat.2006.01.006
  • Calibration of MOSFET detectors for absolute dosimetry with an (IR)-I-192 HDR brachytherapy source Zilio V, Joneja O, Popowski Y, Rosenfeld A, Chawla R
    STRAHLENTHERAPIE UND ONKOLOGIE 182, 175-175 (2006).
  • Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems Mikityuk K, Coddington P, Bubelis E, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 236, 2452-2473 (2006).
    DOI: 10.1016/j.nucengdes.2006.03.012
  • Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades Plaschy Michael, Jatuff Fabian, Grimm Peter, Tani Filippo, Jacot-Guillarmod Roland, Giust Flavio, Krouthen Jan, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43, 1298-1310 (2006).
    DOI: 10.3327/jnst.43.1298
  • Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10X10 BWR assembly Jatuff F, Giust F, Krouthen J, Helmersson S, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 119-125 (2006).
    DOI: 10.1016/j.anucene.2005.09.007
  • Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, Chawla R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43, 223-230 (2006).
    DOI: 10.3327/jnst.43.223
  • HTGR reactor physics and fuel cycle studies Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten HJ, Brockmann H, Damian F, Dolci F, Bernnat W, Oppe J, Kloosterman JL, Cerullo N, Lomonaco G, Negrini A, Magill J, Seiler R
    NUCLEAR ENGINEERING AND DESIGN 236, 615-634 (2006).
    DOI: 10.1016/j.nucengdes.2005.10.021
  • Implications of alternative strategies for transition to sustainable fuel cycles Romano Antonino, Boscher Thomas, Hejzlar Pavel, Kazimi Mujid S, Todreas Neil E
    NUCLEAR SCIENCE AND ENGINEERING 154, 1-27 (2006).
  • Investigations on the stability of the flow characteristics in a bubble column Lucas Dirk, Krepper Eckhard, Prasser Horst-Michael, Manera Annalisa
    CHEMICAL ENGINEERING & TECHNOLOGY 29, 1066-1072 (2006).
    DOI: 10.1002/ceat.200600150
  • Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry Wenger HU, Al Mazouzi A, Atchison F, Burghartz M, Chawla R, Gunther-Leopold I, Heimgartner P, Hellwig C, Ingold F, Kopajtic Z, Linder HP
    NUCLEAR PHYSICS A 764, 1-14 (2006).
    DOI: 10.1016/j.nuclphysa.2005.08.023
  • Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code Romano A, Wallin H, Zimmermann MA, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 236, 284-294 (2006).
    DOI: 10.1016/j.nucengdes.2005.08.007
  • On the accuracy of reactor physics calculations for square HPLWR fuel assemblies Jatuff F, Macku K, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 198-207 (2006).
    DOI: 10.1016/j.anucene.2005.09.006
  • On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores Pelloni Sandro, Coddington Paul
    ANNALS OF NUCLEAR ENERGY 33, 1360-1367 (2006).
    DOI: 10.1016/j.anucene.2006.10.001
  • Optimised non-invasive method to determine U-238-captures-to-total-fissions in reactor fuel Bergmann UC, Chawla R, Jatuff F, Murphy MF
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 556, 331-338 (2006).
    DOI: 10.1016/j.nima.2005.08.110
  • RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark Barten W, Coddington P, Ferroukhi H
    ANNALS OF NUCLEAR ENERGY 33, 99-118 (2006).
    DOI: 10.1016/j.anucene.2005.09.011
  • Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples Murphy M F, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, Berger H-D, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 760-765 (2006).
    DOI: 10.1016/j.anucene.2006.04.003
  • Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation Dokhane A, Ferroukhi H, Zimmermann M A, Aguirre C
    ANNALS OF NUCLEAR ENERGY 33, 1329-1338 (2006).
    DOI: 10.1016/j.anucene.2006.08.010
  • Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+BWR assembly Tani F, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 490-498 (2006).
    DOI: 10.1016/j.anucene.2006.02.005
  • Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis Ma WM, Bubelis E, Karbojian A, Sehgal BR, Coddington P
    NUCLEAR ENGINEERING AND DESIGN 236, 1422-1444 (2006).
    DOI: 10.1016/j.nucengdes.2006.01.006
Top

2005

  • (CE)-C-144 as a potential candidate for interstitial and intravascular brachytherapy Zilio VO, Joneja OP, Popowski Y, Bochud FO, Chawla R
    INTERNATIONAL JOURNAL OF RADIATION ONCOLOGY BIOLOGY PHYSICS 62, 585-594 (2005).
    DOI: 10.1016/j.ijrobp.2005.02.005
  • A polynomial form for higher-order accurate quantification of perturbation effects in nuclear systems van Geemert R, Tani F
    NUCLEAR SCIENCE AND ENGINEERING 149, 74-87 (2005).
  • Development of a drift-flux model for heavy liquid metal/gas flow Mikityuk K, Coddington P, Chawla R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 42, 600-607 (2005).
    DOI: 10.3327/jnst.42.600
  • FAST: An advanced code system for fast reactor transient analysis Mikityuk K, Pelloni S, Coddington P, Bubelis E, Chawla R
    ANNALS OF NUCLEAR ENERGY 32, 1613-1631 (2005).
    DOI: 10.1016/j.anucene.2005.06.002
  • Importance of the MUSE experiments for emerging ADS concepts from the nuclear data viewpoint Plaschy M, Pelloni S, Coddington P, Rimpault G, Chawla R
    ANNALS OF NUCLEAR ENERGY 32, 843-856 (2005).
    DOI: 10.1016/j.anucene.2005.01.001
  • Investigation of ADS-type heterogeneities in the MUSE4 critical configuration Plaschy M, Destouches C, Rimpault G, Chawla R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 42, 779-787 (2005).
    DOI: 10.3327/jnst.42.779
  • Natural circulation and stability performance of BWRs (NACUSP) Aguirre C, Caruge D, Castrillo F, Dominicus G, Geutjes AJ, Saldo V, van der Hagen THJJ, Hennig D, Huggenberger M, Ketelaar KCJ, Manera A, Munoz-Cobo JL, Prasser HM, Rohde U, Royer E, Yadigaroglu G
    NUCLEAR ENGINEERING AND DESIGN 235, 401-409 (2005).
    DOI: 10.1016/j.nucengdes.2004.08.048
  • Nuclear power and CO2 Chawla R
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER 50, 306-+ (2005).
  • Review of the licensing basis for RIA and LOCA transients in light of new evidence on high burnup fuel behavior Zimmermann MA, Bart G
    CHIMIA 59, 950-956 (2005).
    DOI: 10.2533/000942905777675291
  • Semi-analytical bifurcation analysis of two-phase flow in a heated channel Dokhane A, Hennig D, Chawla R, Rizwan-Uddin
    INTERNATIONAL JOURNAL OF BIFURCATION AND CHAOS 15, 2395-2409 (2005).
    DOI: 10.1142/S0218127405013381
  • Static Analysis of the PDS-XADS LBE and Gas-Cooled Concepts Pelloni S
    ANNALS OF NUCLEAR ENERGY 32, 13 (2005).
    DOI: 10.1016/j.anucene.2004.08.004
  • Within-pin reaction rate distributions: CASMO-4 and HELIOS compared against tomographic measurements at the PROTEUS reactor Fauchere CP, Murphy M, Jatuff F, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 150, 27-36 (2005).
Top

2004

  • Adapting and applying SPECT to the investigation of reaction rate distributions within lightly activated nuclear fuel pins Fauchere CP, Jatuff F, Murphy M, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 522, 579-590 (2004).
    DOI: 10.1016/j.nima.2003.12.001
  • Development and application of a decomposition methodology for interpretation of reactivity effect discrepancies van Geemert R, Jatuff F, Tani F, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 148, 162-171 (2004).
  • Development, assessment and application of TRAC-BF1/v2001.2 for beyond design basis BWR LOCA transients Analytis GT, Coddington P
    ANNALS OF NUCLEAR ENERGY 31, 517-540 (2004).
    DOI: 10.1016/j.anucene.2003.09.002
  • Experimental determination of the ratio of U-238 capture to U-235 fission in LEU-HTR pebble-bed configurations Koberl O, Seiler R, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 146, 1-12 (2004).
  • Peach bottom BWR turbine trip benchmark analyses with RETRAN-3D and CORETRAN Barten W, Ferroukhi H, Coddington P
    NUCLEAR SCIENCE AND ENGINEERING 148, 306-324 (2004).
  • Plutonium management in the medium term Hesketh K, Schlosser G, Porsch DF, Wolf T, Koberl O, Lance B, Chawla R, Gehin JC, Ellis R, Uchikawa S, Sato O, Okubo T, Mineo H, Yamamoto T, Sagayama Y, Sartori E
    NUCLEAR TECHNOLOGY 148, 244-258 (2004).
  • Quantification of the transferability of reactivity effect investigations in large multiregion systems van Geemert R, Jatuff F, Tani F, Chawla R
    ANNALS OF NUCLEAR ENERGY 31, 1735-1763 (2004).
    DOI: 10.1016/j.anucene.2004.05.001
  • Validation of new electron and positron data libraries Negreanu C, Stepanek J, Joneja OP, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS 213, 55-59 (2004).
    DOI: 10.1016/S0168-583X(03)01533-7
  • Void fraction and critical power assessment of CORETRAN-01/VIPRE-02 Aounallah Y
    NUCLEAR TECHNOLOGY 145, 163-176 (2004).
Top

2003

  • Assessment of RETRAN-3D boiling models against experimental subcooled boiling tube data Macian R, Coddington P, Stangroom P
    NUCLEAR TECHNOLOGY 142, 47-63 (2003).
  • Comparison of various partial light water reactor core loadings with inert matrix and mixed-oxide fuel Kasemeyer U, Hellwig C, Lebenhaft J, Chawla R
    JOURNAL OF NUCLEAR MATERIALS 319, 142-153 (2003).
    DOI: 10.1016/S0022-3115(03)00146-6
  • Interpretation of experimental results from moderate-power in-pile testing of a Pu-Er-Zr-oxide inert matrix fuel Hellwig C, Kasemeyer U, Ledergerber G, Lee BH, Lee YW, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 287-299 (2003).
    DOI: 10.1016/S0306-4549(02)00059-2
  • Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation Jatuff F, Luthi A, Murphy M, Williams T, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 1731-1755 (2003).
    DOI: 10.1016/S0306-4549(03)00136-1
  • Planned experimental studies on natural-circulation and stability performance of boiling water reactors in four experimental facilities and first results (NACUSP) de Kruijf WJM, Ketelaar KCJ, Avakian G, Gubernatis P, Caruge D, Manera A, Van der Hagen THJJ, Yadigaroglu G, Dominicus G, Rohde U, Prasser HM, Castrillo F, Huggenberger M, Hennig D, Munoz-Cobo JL, Aguirre C
    NUCLEAR ENGINEERING AND DESIGN 221, 241-250 (2003).
    DOI: 10.1016/S0029-5493(02)00338-2
  • Sensitivities of the proton beam current resulting from variations in the source term for a Pb-Bi cooled accelerator driven system with a Pb-Bi Target Pelloni S
    ANNALS OF NUCLEAR ENERGY 30, 983-1000 (2003).
    DOI: 10.1016/S0306-4549(03)00011-2
  • The analysis of pressurized water reactor and boiling water reactor reactivity transients with CORETRAN and RETRAN-3D Ferroukhi H, Coddington P
    NUCLEAR TECHNOLOGY 142, 19-34 (2003).
  • Trends and needs in experimentation and numerical simulation for LWR safety Yadigaroglu G, Andreani M, Dreier J, Coddington P
    NUCLEAR ENGINEERING AND DESIGN 221, 205-223 (2003).
    DOI: 10.1016/S0029-5493(02)00339-4
  • Validation of axial pin power distributions in a 10 x 10 BWR assembly across an enrichment boundary under full-density water moderation conditions Jatuff F, Grimm P, van Geemert R, Murphy M, Seiler R, Brogli R, Giust F, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 911-930 (2003).
    DOI: 10.1016/S0306-4549(02)00144-5
Top

2002

  • A nodal modal method for the neutron diffusion equation. Application to BWR instabilities analysis Miro R, Ginestar D, Verdu G, Hennig D
    ANNALS OF NUCLEAR ENERGY 29, 1171-1194 (2002).
    DOI: 10.1016/S0306-4549(01)00103-7
  • A novel auto-correlation function method for the determination of the decay ratio in BWR stability analysis Behringer K, Hennig D
    ANNALS OF NUCLEAR ENERGY 29, 1483-1504 (2002).
    DOI: 10.1016/S0306-4549(01)00122-0
  • A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models Coddington P, Macian R
    NUCLEAR ENGINEERING AND DESIGN 215, 199-216 (2002).
    DOI: 10.1016/S0029-5493(01)00503-9
  • A transient modal analysis of a BWR instability event Ginestar D, Miro R, Verdu G, Hennig D
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 39, 554-563 (2002).
    DOI: 10.3327/jnst.39.554
  • Analysis and sensitivity studies of postulated SB-LOCAs in the Muhleberg (KKM) BWR/4 by TRAC-BF1 Analytis GT, Coddington P
    ANNALS OF NUCLEAR ENERGY 29, 1525-1549 (2002).
    DOI: 10.1016/S0306-4549(01)00123-2
  • Application and in-depth assessment of RETRAN-3D for best estimate analysis of nuclear power plant transients Coddington P, Macian R, Zimmermann MA, Chawla R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 39, 972-985 (2002).
    DOI: 10.3327/jnst.39.972
  • Assessment of reactivity effects due to localized perturbations in BWR lattices van Geemert R, Jatuff F, Grimm R, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 142, 96-106 (2002).
  • Feasibility of partial LWR core loadings with inert-matrix fuel Kasemeyer U, Hellwig C, Dean DW, Chawla R, Meier G, Williams T
    ADVANCED REACTORS WITH INNOVATIVE FUELS, WORKSHOP PROCEEDINGS , 245-260 (2002).
  • Neutronics investigations for the lower part of a westinghouse SVEA-96+assembly Murphy MF, Luthi A, Seiler R, Grimm P, Joneja O, Meister A, van Geemert R, Jatuff F, Brogli R, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 141, 32-45 (2002).
  • Simulation and analysis of experimental blowdown and small-break loss-of-coolant scenarios with RETRAN-3D Macian R, Coddington P
    NUCLEAR TECHNOLOGY 139, 185-204 (2002).
Top

2001

  • A numerical neutronics benchmark study for inert matrix plutonium fuels in uranium dioxide and mixed plutonium-uranium dioxide environments Paratte JM, Chawla R, Akie H, Damen PMG, Joo HK, Mikolas P, Padovani E, Peneliau Y, Youinou G
    PROGRESS IN NUCLEAR ENERGY 38, 335-342 (2001).
    DOI: 10.1016/S0149-1970(00)00130-X
  • Categorisation and priorities for future research on inert matrix fuels: An extended synthesis of the panel discussions Chawla R, Konings RJM
    PROGRESS IN NUCLEAR ENERGY 38, 455-458 (2001).
    DOI: 10.1016/S0149-1970(00)00157-8
  • Importance of zirconium cross sections in calculating reactivity effects for inert matrix fuels Baldi S, Porta J, Peneleau Y, Pelloni S, Paratte JM, Chawla R
    PROGRESS IN NUCLEAR ENERGY 38, 351-354 (2001).
    DOI: 10.1016/S0149-1970(00)00133-5
  • Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations Luthi A, Chawla R, Rimpault G
    NUCLEAR SCIENCE AND ENGINEERING 138, 233-255 (2001).
  • Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice Chawla R, Grimm P, Heimgartner P, Jatuff F, Ledergerber G, Luthi A, Murphy M, Seiler R, van Geemert R
    PROGRESS IN NUCLEAR ENERGY 38, 359-362 (2001).
    DOI: 10.1016/S0149-1970(00)00135-9
  • LWR-PROTEUS verification of reaction rate distributions in modern 10 x 10 boiling water reactor fuel Jatuff F, Grimm R, Joneja O, Murphy M, Luthi A, Seiler R, Brogli R, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 139, 262-272 (2001).
  • The physical mechanism of core-wide and local instabilities at the Forsmark-1 BWR (vol 205, pg 91, 2001) Analytis GT, Hennig D, Karlsson JKH
    NUCLEAR ENGINEERING AND DESIGN 210, 265-265 (2001).
    DOI: 10.1016/S0029-5493(01)00381-8
  • Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries Joneja OP, Plaschy M, Jatuff F, Luthi A, Murphy M, Seiler R, Chawla R
    ANNALS OF NUCLEAR ENERGY 28, 701-713 (2001).
    DOI: 10.1016/S0306-4549(00)00079-7
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2000

  • Characterisation of MCP-7s material for use as a beta extremity dosemeter Boschung M, Homsy A, Joneja OP, Chawla R
    RADIATION PROTECTION DOSIMETRY 92, 313-318 (2000).
    DOI: 10.1093/oxfordjournals.rpd.a033298
  • Comparisons of cell calculations for uranium-free light water reactor fuels Paratte JM, Akie H, Chawla R, Delpech M, Kloosterman JL, Lombardi C, Mazzola A, Pelloni S, Peneliau Y, Takano H
    NUCLEAR TECHNOLOGY 130, 159-176 (2000).
  • Epithermal inverse kinetic measurements and their interpretation using a two-group point-kinetic model Rosselet M, Chawla R, Williams T
    NUCLEAR SCIENCE AND ENGINEERING 135, 33-47 (2000).
  • On the regional oscillation phenomenon in BWR's (vol 36, pg 189, 2000) Miro R, Ginestar D, Hennig D, Verdu G
    PROGRESS IN NUCLEAR ENERGY 36, 469-469 (2000).
    DOI: 10.1016/S0149-1970(00)00014-7
  • On the regional oscillation phenomenon in BWR's. Miro R, Ginestar D, Hennig D, Verdu G
    PROGRESS IN NUCLEAR ENERGY 36, 189-229 (2000).
    DOI: 10.1016/S0149-1970(00)00005-6

1999

  • A high-fluence 0.6 GeV proton irradiation experiment with thin uranium and thorium targets Wenger HU, Botta F, Chawla R, Gavillet D, Kopajtic Z, Ledergerber G, Linder H, Rollin S
    ANNALS OF NUCLEAR ENERGY 26, 141-148 (1999).
    DOI: 10.1016/S0306-4549(98)89001-4
  • A study on boiling water reactor stability behavior Hennig D
    NUCLEAR TECHNOLOGY 126, 10-31 (1999).
  • Conceptual studies for pressurised water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies Stanculescu A, Kasemeyer U, Paratte JM, Chawla R
    JOURNAL OF NUCLEAR MATERIALS 274, 146-152 (1999).
    DOI: 10.1016/S0022-3115(99)00082-3
  • Evaluation of the slip options in RETRAN-3D Maier D, Coddington P
    NUCLEAR TECHNOLOGY 128, 153-168 (1999).
  • Implementation of an improved interfacial mass and energy transfer model in RETRAN-3D Macian R, Cebull P, Coddington P, Paulsen M
    NUCLEAR TECHNOLOGY 128, 139-152 (1999).
  • Investigation of the k(eff)-variation upon water ingress in a pebble-bed LEU-HTR Rosselet M, Chawla R, Williams T
    ANNALS OF NUCLEAR ENERGY 26, 75-82 (1999).
    DOI: 10.1016/S0306-4549(98)80001-7
  • Time-dependent boundary source term for advanced nodal diffusion theory Jatuff FE, Gho CJ
    ANNALS OF NUCLEAR ENERGY 26, 1065-1082 (1999).
    DOI: 10.1016/S0306-4549(98)00102-9
  • VIPRE-02 subchannel validation against NUPEC BWR void fraction data Aounallah Y, Coddington P
    NUCLEAR TECHNOLOGY 128, 225-232 (1999).
  • Validation efforts for the neutronics of a plutonium-erbium-zirconium oxide inert matrix light water reactor fuel Paratte JM, Chawla R, Fruh R, Joneja OP, Pelloni S, Pralong C
    JOURNAL OF NUCLEAR MATERIALS 274, 120-126 (1999).
    DOI: 10.1016/S0022-3115(99)00086-0
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1998

  • Impact of methods and data on calculational results for LWR lattices employing uranium-free plutonium fuels Pelloni S, Kasemeyer U, Paratte JM, Chawla R
    KERNTECHNIK 63, 239-248 (1998).
  • Some comments on the physical mechanism causing oscillatory instabilities in boiling water reactors
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS , 25-28 (1998).
  • Subcriticality measurements using an epithermal Pulsed-Neutron-Source technique in pebble-bed HTR configurations Rosselet M, Williams T, Chawla R
    ANNALS OF NUCLEAR ENERGY 25, 285-294 (1998).
    DOI: 10.1016/S0306-4549(97)00059-5

1997

  • Planning calculations for new LWR experiments at the PROTEUS facility Ziver A, Brogli R, Chawla R, Grimm P, Hager H, Seiler R, Williams T
    JAHRESTAGUNG KERNTECHNIK '97 , 19-22 (1997).
  • Void coefficient analysis of an LWR lattice experiment with high-enrichment MOX fuel Bohme R, Berger HD, Chawla R, Hager H, Seiler R, Williams T
    NUCLEAR ENGINEERING AND DESIGN 168, 271-279 (1997).
    DOI: 10.1016/S0029-5493(96)00002-7

1996

  • Analysis of a main steam isolation valve closure transient without scram for a BWR/6 Mark-III plant Coddington P, Wand H
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '96 , 163-167 (1996).

1995

  • ON THE PHYSICS FEASIBILITY OF LWR PLUTONIUM FUELS WITHOUT URANIUM PARATTE JM, CHAWLA R
    ANNALS OF NUCLEAR ENERGY 22, 471-481 (1995).
    DOI: 10.1016/0306-4549(94)00061-I

1992

  • ANALYSIS OF PROTEUS PHASE-II EXPERIMENTS IN SUPPORT OF LIGHT WATER HIGH CONVERSION REACTOR DESIGN CHAWLA R, BOHME R, ALFONSO J, AXMANN J, BERGER HD, HAGER H, PELLONI S, SEILER R, WILLIAMS T
    KERNTECHNIK 57, 14-22 (1992).
  • EXPERIMENTAL COMPARISONS FOR BOTTOM REFLOODING IN TIGHT LWHCR AND STANDARD LWR GEOMETRIES ROUGE N, DREIER J, YANAR S, CHAWLA R
    NUCLEAR ENGINEERING AND DESIGN 137, 35-47 (1992).
    DOI: 10.1016/0029-5493(92)90046-X
  • TRANSIENT ANALYSIS OF THE MSIV-ATWS IN A 1000-MW(THERMAL) BWR-4 ZIMMERMANN MA
    NUCLEAR TECHNOLOGY 100, 184-192 (1992).

1991

  • LEU-HTR CRITICAL EXPERIMENT PROGRAM FOR THE PROTEUS FACILITY IN SWITZERLAND BROGLI R, BUCHER KH, CHAWLA R, FOSKOLOS K, LUCHSINGER H, MATHEWS D, SARLOS G, SEILER R
    ENERGY 16, 507-519 (1991).
    DOI: 10.1016/0360-5442(91)90130-E

1987

  • NUCLEATE BOILING AND THE CHEN CORRELATION FOR FLOW BOILING HEAT TRANSFER Aounallah Y, Kenning D B R
    EXPERIMENTAL HEAT TRANSFER 1, 87-92 (1987).

1980

  • DIRECT DETERMINATION OF THE RATIO OF TH-232 (N, 2N) AND (N, GAMMA) REACTIONS IN A FAST-REACTOR CHAWLA R, GMUR K, GORLICH W
    NUCLEAR INSTRUMENTS & METHODS 174, 179-182 (1980).
    DOI: 10.1016/0029-554X(80)90428-0