Source: https://www.psi.ch/de/fast/publications
Timestamp: 2019-04-23 22:38:35+00:00

Document:
K. Mikityuk, A. Chenu, K. Sun.
"Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics"
"Single- and Two-Phase Flow Modelling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors"
"Improvement of the Inherent and Passive Safety Characteristics of Generation IV Gas-cooled Fast Reactor"
"Development of the Control Assembly Pattern and Dynamic Analysis of the Generation IV Large Gas-cooled Fast Reactor (GFR)"
"Development and Application of an Advanced Fuel Model for the Safety Analysis of the Generation IV Gas-cooled Fast Reactor"
"Analytical and experimental study of chugging boiling instability: the CHUG project"
"Development of a Dedicated Burnup Tool for Molten Salt Fast Reactor"
"Development of a CAD model for the European Sodium Fast Reactor in view of using the thermal hydraulics code TRACE"
"Modelling of the low-void SFR core during ULOF with spatial kinetics"
"Statistical burnup distribution of moving pebbles in HTR-PM reactor"
"Coupled multi-physics simulations of the Molten Salt Fast Reactor using coarse-mesh thermal-hydraulics and spatial neutronics"
"Development of the model for the multiphysics analysis of Molten Salt Reactor Experiment using GeN-Foam code"
"CFD simulations of sodium two-phase flows"
"Static and transient analysis of Molten Salt Reactor Experiment using SERPENT-2/TRACE/PARCS codes"
"Empirical Decay Heat Correlations and Fission Products Behavior in MSRs"
"Time efficient fluid dynamics analysis of sodium fast reactor wire wrapped rod bundles"
"Static neutronic, thermal-hydraulic and fuel performance analysis of the ASTRID Sodium-cooled Fast Reactor core"
"Heat exchanger analysis for innovative molten salt fast reactor"
"Parametric Lattice Study for Conception of a Molten Salt Reactor in Closed Thorium Fuel Cycle"
"Development of SERPENT based equilibrium fuel cycle procedure EQL0D"
"Use of Serpent Monte-Carlo code for development of 3D full-core models of Gen-IV fast-spectrum reactors and preparation of group constants for transiet analyses with PARCS/TRACE coupled system"
"Development of a new method for dynamic reactivity decomposition"
"Approaching the equilibrium closed fuel cycle in advanced fast reactors"
"Development of a full-core ERANOS Model and neutronic analysis of the BN-600 Fast Reactor Core Mock-up at the BFS-2 zero-power facility"
"Comparative decomposition analysis of reactivity effects for the main Gen-IV fast reactors"
"Coupled Neutronic/Thermal-hydraulic Simulation of Selected PHENIX End-of-life Tests"
"Simulation of CABRI loss-of-flow experiments with the TRACE/FRED codes"
"Neutronic Analysis of the European Gas-Cooled Fast Reactor Demonstrator ALLEGRO and its Validation via Monte Carlo TRIPOLI Calculations"
"Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data"
"Simulations of advanced reactor cores in research light water reactor LR-0"
"Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores"
"Monte Carlo nuclear data adjustment via integral information"
"Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments"
"Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification"
"Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments"
"Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology"
"System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions"
"Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems"
"Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform"
"Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels"
"Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data"
"The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe -- Part II: Thorium fuel cycle"
"Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels"
"GeN-Foam: a novel OpenFOAM(R) based multi-physics solver for 2D/3D transient analysis of nuclear reactors"
"On the use of the SPH method in nodal diffusion analyses of SFR cores"
"The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe -- Part I: Uranium fuel cycle"
"A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT"
"Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor"
"Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor"
"Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems"
"A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics"
"The core design of ALFRED, a demonstrator for the Europeanlead-cooled reactors"
"Code assessment and modelling for Design Basis Accident analysis ofthe European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis"
"Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors"
C. Fiorina, A. Cammi, L. Luzzi, K. Mikityuk, H. Ninokata and M. E. Ricotti.
"Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor"
J. Krepel, B. Hombourger, C. Fiorina, K. Mikityuk, U. Rohde, S. Kliem, A. Pautz.
"Fuel cycle advantages and dynamics features of liquid fueled MSR"
A. Lázaro, L. Ammirabile, G. Bandini, G. Darmet, S. Massara, Ph. Dufour, A. Tosello, E. Gallego, G. Jimenez, K. Mikityuk, M. Schikorr, E. Bubelis, A. Ponomarev, R. Kruessmann, M. Stempniewicz.
"Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking"
Nuclear Engineering and Design 266 (2014) 1-16.
M. Salvatores, G. Palmiotti, G. Aliberti, P. Archier, C. De Saint Jean, E. Dupont, M. Herman, M. Ishikawa, T. Ivanova, E. Ivanov, S.-J. Kim, I. Kodeli, G. Manturov, R. McKnight, S. Pelloni, C. Perfetti, A.J.M. Plompen, B.T. Rearden, D. Rochman, K. Sugino, A. Trkov, W. Wang, H. Wu, and W.-S. Yang.
"Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study"
J. Lüley, B. Vrban, S. Cerba,J. Hascik, V. Necas, and S. Pelloni.
"Sensitivity and Uncertainty Analysis of the GFR MOX Fuel Subassembly"
"Application of an iterative methodology for cross-section and variance/covariance data adjustment to the analysis of fast spectrum systems accounting for non-linearity" Annals of Nuclear Energy 72 (2014) 373-390.
C. Fiorina, M. Aufiero, A. Cammi, F. Franceschini, J. Krepel, L. Luzzi, K. Mikityuk, M.E. Ricotti.
"Investigation of the MSFR core physics and fuel cycle characteristics"
K. Sun, A. Chenu, J. Krepel, K. Mikityuk, R. Chawla.
"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"
D. Tenchine, D. Pialla, T.H. Fanning, J.W. Thomas, P. Chellapandi, Y. Shvetsov, L. Maas, H.-Y. Jeong, K. Mikityuk, A. Chenu, H. Mochizuki, S. Monti.
"International benchmark on the natural convection test in Phenix reactor"
Nuclear Engineering and Design 258 (2013) 189-198.
K. Sun, J. Krepel, K. Mikityuk, R. Chawla.
"A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor"
Annals of Nuclear Energy, Volume 53, March 2013, Pages 464-475.
C. Fiorina, J. Krepel, A. Cammi, F. Franceschini, K. Mikityuk, M. E. Ricotti.
"Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure"
Annals of Nuclear Energy 53, March 2013 492-506.
C. Fiorina, N.E. Stauff, F. Franceschini, M.T. Wenner, A. Stanculescu, T.K. Kim, A. Cammi, M.E. Ricotti, R.N. Hill, T.A. Taiwo, M. Salvatores.
"Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor"
Annals of Nuclear Energy 62 (2013) 26-39.
A. Chenu, R. Adams, K. Mikityuk, R. Chawla.
"Analysis of selected Phenix EOL tests with the FAST code system -- Part I: Control-rod-shift experiments"
Annals of Nuclear Energy. Volume 49, November 2012, Pages 182-190.
A. Chenu, K. Mikityuk, R. Chawla.
"Analysis of selected Phenix EOL tests with the FAST code system -- Part II: Unprotected phase of the Natural Convection Test"
Annals of Nuclear Energy. Volume 49, November 2012, Pages 191-199.
J. Krepel, S. Pelloni, K. Mikityuk.
"Comparison of open and closed U-Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure"
Nuclear Engineering and Design, Volume 250, September 2012, Pages 392-402.
A. Marinoni, G. Girardin, K. Mikityuk.
"Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX"
Annals of Nuclear Energy 44 (2012) 26-33.
A. Epiney, N. Alpy, K. Mikityuk, R. Chawla.
"A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions"
Nuclear Engineering and Design, Volume 242, January 2012, Pages 267-284.
G. Khvostov, K. Mikityuk, M.A. Zimmermann.
"A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code"
Nuclear Engineering and Design, Volume 241, Issue 8, August 2011, Pages 2983-3007.
R. Stainsby, K. Peers, C. Mitchell, C. Poette, K. Mikityuk, J. Somers.
"Gas cooled fast reactor research in Europe"
"Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow"
K. Sun, J. Krepel, K. Mikityuk, S. Pelloni, R. Chawla.
"Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle"
Annals of Nuclear Energy 38 (2011) 1645-1657.
K. Mikityuk and A. Shestopalov.
"FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests"
Nuclear Engineering and Design 241 (2011) 2455-2461.
S. Pelloni and K. Mikityuk.
"A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors"
A. Epiney, K. Mikityuk, R. Chawla.
"Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions"
"Analytical model of the oxide layer build-up in complex lead-cooled systems"
K. Mikityuk, J. Krepel, S. Pelloni, A. Chenu, P. Petkevich, R. Chawla.
"FAST Code System: Review of Recent Developments and Near-Future Plans"
"TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods"
Annals of Nuclear Energy, Volume 37, Issue 6, June 2010, Pages 875-887.
J. Krepel, S. Pelloni, K. Mikityuk, P. Coddington.
"GFR equilibrium cycle analysis with the EQL3D procedure"
Nuclear Engineering and Design, Volume 240, Issue 4, April 2010, Pages 905-917.
"Gas Cooled Fast Reactor Research and Development in the European Union"
A. Chenu, K. Mikityuk and R. Chawla.
"TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions"
Nuclear Engineering and Design. Volume 239, Issue 11, November 2009, Pages 2417-2429.
P. Petkevich, K. Mikityuk, P. Coddington, R. Chawla.
"Development and benchmarking of a mechanical model for GFR plate-type fuel"
"EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors"
Annals of Nuclear Energy, 36, Issue 5, (2009), Pages 550-561.
"Heat transfer to liquid metal: Review of data and correlations for tube bundles"
Nuclear Engineering and Design 239 (2009) 680-687.
E. Bubelis, D. Castelliti, P. Coddington, I, Dor, C. Fouillet, E. de Geus, T. Marshall, W. van Rooijen, M. Schikorr, R. Stainsby.
"A GFR benchmark: Comparison of transient analysis codes based on the ETDR concept"
E. Bubelis, P. Coddington, K. Mikityuk.
"Verification of the TRACE Code against the MEGAPIE Transient Data"
G. Girardin, G. Rimpault, F. Morin, J. Bosq, P. Coddington, K. Mikityuk, R. Chawla.
"Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor"
J. Krepel, U. Rohde, U. Grundmann, F.P. Weiss.
"Dynamics of molten salt reactors"
K. Mikityuk, P. Coddington, F. Gröschel.
"Analysis of radioactivity releases in the MEGAPIE reference accident"
"Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel"
K. Mikityuk, P. Coddington, S. Pelloni, E. Bubelis, R. Chawla.
"Comparative Transient Analysis of Critical and Subcritical 80-MW Pb-Bi Eutectic-cooled Reactor Systems"
K. Mikityuk, P. Coddington, E. Bubelis, R. Chawla.
"Comparison of the Transient Behaviour of LBE- and Gas-Cooled Experimental Accelerator-Driven Systems"
S. Pelloni, E. Bubelis, K. Mikityuk, P. Coddington.
"Calculations of Reactivity-Initiated Transients in Gas-Cooled Fast Reactors Using the Code System FAST"
W. Ma, E. Bubelis, A. Karbojian, B. Sehgal., P. Coddington.
"Transient Experiments from the Thermal-Hydraulic ADS Lead Bismuth Loop (TALL) and Comparative TRAC/AAA Analysis"
"On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores"
K. Mikityuk, S. Pelloni, P. Coddington, E. Bubelis, R. Chawla.
"FAST: An Advanced Code System for FAST Reactor Transient Analysis"
K. Mikityuk, P. Coddington, R. Chawla.
"Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow"
"Static Analysis of the PDS-XADS LBE and Gas-Cooled Concepts"
M. Plaschy, S. Pelloni, P. Coddington, G. Rimpault, R. Chawla.
"Importance of the MUSE Experiments for Emerging ADS Concepts from the Nuclear Data Viewpoint"
"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"
Annals of Nuclear Energy 30 (2003) 983-1000.
"Proposal of new safety measures for European Sodium Fast Reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project"
"New sodium fast reactor neutronics benchmark"
"Core safety measures in ESFR-SMART"
"Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code"
"A simplified numerical benchmark for pool-type Sodium Fast Reactors"
"Use of CAD models in ESFR-SMART project"
"New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project"
"Fuel cycle sustainability of molten salt reactor concepts in comparison with other selected reactors"
"Mixed LEU-Th Initial Core and Running-In Phase for the HTR-PM Reactor"
"Analysis of major group structures used for nuclear reactor simulations"
"Benchmark Analyses of EBR-II Shutdown Heat Removal Tests"
"GEN IV Education and Training Initiative via Public Webinars"
"Low-void-effect sodium-cooled core: Uncertainty of local sodium void reactivity as a result of nuclear data uncertainties"
"Simulating Circulating-Fuel Fast Reactors with the Coupled TRACE-PARCS Code"
"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)"
"IAEA's Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview"
"Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment"
"On the Feasibility of Breed-and-Burn Fuel Cycles in Molten Salt Reactors"
"ESFR-SMART: new Horizon-2020 project on SFR safety"
"Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow"
"Comparison of fast reactors performance in the closed U-Pu and Th-U cycle"
"IAEA Neutronics Benchmark for EBR-II SHRT-45R"
"Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor"
"Enumeration of static and dynamic neutron consumption D-factor for several selected reactors at equilibrium closed fuel cycle"
"The EQL0D procedure for fuel cycle studies in molten salt reactor"
"A progressive incremental adjustment methodology for cross-section and variance/covariance data adjustment for fast-spectrum systems"
"Neutronics Benchmark for EBR-II Shutdown Heat Removal Test SHRT-45R"
"GeN-Foam: a novel multi-physics solver for reactor analysis -- Status and ongoing developments"
Proceedings of ANS Winter 2015 Meeting, November 8-12, 2015, Washington, DC.
"Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor"
Proceedings of TopFuel 2015 Conference, September 13-17, 2015, Zurich, Switzerland.
"Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation"
"Comparison of Several Recycling Strategies and Relevant Fuel Cycles for Molten Salt Reactor"
"The European Project ESNII Plus"
"Extension of the FAST code system for the modelling and simulation of MSR dynamics"
"Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes"
"Validation of the Serpent and TRACE codes using the SHRT-17 and SHRT-45R loss-of-flow tests performed in the EBR-II reactor"
"Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor"
"Fuel cycle analysis of a molten salt reactor for breed-and-burn mode"
"SERPENT-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst"
"Analysis of Axial Fuel Relocation Based on Gamma Scan Data from OECD Halden Reactor Project LOCA Tests"
"Hybrid spectrum molten salt reactor"
"Methodology assessment for the evaluation of the coolant void worth in sodium fast reactor with a low void effect core design"
"An innovative approach to dynamic modeling and simulation of the molten salt reactor experiment"
"IAEA benchmark calculations on control rod withdrawal test performed during Phenix-End-Of-Life experiments -- benchmark results and comparison"
C. Fiorina, K. Mikityuk, J. Krepel.
"A procedure for the pre-conceptual design of fast reactors and application to a gas-cooled sub-critical transmuter"
B. Hombourger, J. Krepel, K. Mikityuk, A. Pautz.
J. Krepel, B. Hombourger, V. Bykov, C. Fiorina, K. Mikityuk, A. Pautz.
"Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning"
C. Fiorina, M. Aufiero, S. Pelloni, K. Mikityuk.
"A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and simulation of a Godiva prompt critical burst"
V. Bykov, J. Krepel, A. Pautz.
"Molten salt fast reactor blanket design and proliferation resistance assessment"
J. Krepel, C. Fiorina, S. Kliem.
"Advantages and Dynamics Features of Liquid Fueled MSR"
Proceedings of Conference on Molten Salts in Nuclear Technology (CMSNT), January 9 - 11, 2013, Bhabha Atomic Research Centre, Mumbai, India.
"New transient analysis of the Superphénix start-up tests"
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), 4-7 March 2013, Paris, France.
K. Mikityuk, J. Krepel, S. Pelloni, G. Girardin, A. Chenu, K. Sun, A. Epiney, R. Adams, L. Ghasabyan, M. Alonso, F. Reiterer.
"FAST Code System: Review of Recent Applications"
K. Mikityuk, Z. Perkó, G. Girardin.
"Reactivity effect of steam/water ingress in Generation-IV Gas-cooled Fast Reactor core"
L. Ghasabyan, K. Mikityuk, J. Krepel, S. Pelloni.
"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"
J. Krepel, V. Brankov, K. Mikityuk.
"Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters"
L. Briggs, C. Choi, W. Hu, L. Maas, W. Maschek, B. Merk, K. Mikityuk, H. Mochizuki, S. Monti, K. Morita, A. Del Nevo, H. Ohira, A. Petruzzi, U. Partha Sarathy, A. Shin, I. Shvetsov, M. Stempniewicz, G. Su, D. Sui, B. Truong.
"Benchmark analyses of the shutdown heat removal tests performed in the EBR-II reactor"
E. Bubelis, M. Schikorr, L. Mansani, G. Bandini, K. Mikityuk, Y. Zhang, G. Geffraye.
"Safety analysis results of the DBC transients performed for the ALFRED reactor"
E. Bubelis, M. Schikorr, M. Frogheri, L. Mansani, G. Bandini, L. Burgazzi, K. Mikityuk, Y. Zhang, R. Lo Frano, N. Forgione.
"LFR safety approach and main ELFR safety analysis results"
G. Grasso, C. Petrovic, K. Mikityuk, D. Mattioli, F. Manni, D. Gugiu.
"Demonstrating the effectiveness of the European LFR concept: the ALFRED core design"
G. Grasso, C. Döderlein, K. Tucek, K. Mikityuk, F. Manni, D. Gugiu.
"A core design approach aimed at the sustainability and intrinsic safety of the European Lead-cooled Fast Reactor"
A. Rineiski, B. Vezzoni, D. Zhang, M. Marchetti, F. Gabrielli, W. Maschek, X.-N. Chen, L. Buiron, J. Krepel, K. Sun, K. Mikityuk, F. Polidoro, D. Rochman, A.J. Koning, D.F. DaCruz, H. Tsige-Tamirat, R. Sunderland.
"ESFR core optimization and uncertainty studies"
B. Vrban, S. Cerba, J. Luley, J. Hascik, V. Necas, S. Pelloni.
"Investigation of the Coupled Reactivity Effects of the Movable Reflector and Safety Control Rods in the GFR"
C. Poette, P. Guedeney, R. Stainsby, K. Mikityuk, S. Knol.
"Gas Cooled Fast Reactors: Recent Advances and Prospects"
M. Salvatores, G. Palmiotti, G. Aliberti, P. Archier, C. De Saint Jean, E. Dupont, M. Herman, M. Ishikawa, T. Ivanova, E. Ivanov, S.-J. Kim, I. Kodeli, G. Manturov, R. McKnight, S. Pelloni, C. Perfetti, A. Plompen, B.T. Rearden, D. Rochman, K. Sugino, A. Trkov, W. Wang, H. Wu, W.-S. Yang.
Proceedings of International Conference on Nuclear Data for Science and Technology (ND-2013). Brookhaven National Laboratory. 4-8 March, 2013, New York City, NY, USA.
J. Luley, B. Vrban, S. Cerba, J. Hascik, V. Necas, S. Pelloni.
J. Krepel, B. Hombourger, K. Mikityuk.
"Dependence of the thorium closed fuel cycle parameters on the moderation level of the molten salt reactor"
V. Pascal, G. Prulhière, B. Fontaine, K. Devan, V. Kriventsev, S.Monti, K. Mikityuk, M. Semenov, T. Taiwo, K. Takano, V. Tiberi.
"Benchmark calculations on control rod withdrawal tests performed during PHENIX end-of-life experiments"
C. Fiorina, A. Cammi, M. E. Ricotti, J. Krepel, K. Mikityuk.
"Analysis of Void Reactivity and Doppler Coefficient for Thorium- And Uranium-Fuelled Lead Fast Reactors"
C. Fiorina, A. Cammi, L. Luzzi, K. Mikityuk, H. Ninokata, M. E. Ricotti.
"MSFR TRU-burining potential and comparison with an SFR"
"The MSFR as a flexible CR reactor: the viewpoint of safety"
"ELECTRA-FORTE, a really small SMR for the Canadian market"
"Modeling issues in small HLMC fast reactors: ELECTRA case study"
"The proto-Earth geo-reactor: a thorium reactor?"
"PSI studies on advanced fuel cycle options for fast/thermal MSR utilizing thorium"
C. Fiorina, M. Aufiero, A. Cammi, C. Guerrieri, J. Krepel, L. Luzzi, K. Mikityuk, M. E. Ricotti.
"Analysis of the MSFR core neutronics adopting different neutron transport models"
"Analysis of Phenix Natural Convection Test with the TRACE code"
G. Girardin, M. Alonso, K. Mikityuk.
" Development of 3D full-core ERANOS-2.2/MCNPX-2.7.0 models and neutronic analysis of the BFS-2- zero-power facility"
K. Sun, A. Chenu, K. Mikityuk, J. Krepel, R. Chawla.
"Coupled 3D-Neutronics / Thermal-Hydraulics Analysis of an Unprotected Loss-of-Flow Accident for a 3600 MWth SFR Core"
"Nuclear Data Uncertainty Analysis for the Generation IV Gas-Cooled Fast Reactor"
"An Optimization Study for Improving the Safety Characteristics of a 3600MWth Sodium-cooled Fast Reactor via Coupled Neutronics/Thermal-Hydraulics Analysis"
Proceedings of International Conference "Nuclear Energy for New Europe", Ljubljana, September 5-7, 2012.
"TRACE analysis of the post dry-out regime in sodium two-phase flow"
Proceedings of ICAPP-11 (May 2-5, 2011, Nice, France).
S. Pelloni, K. Mikityuk and G. Rimpault.
"Nuclear data uncertainty analysis for the Generation IV Sodium-cooled Fast Reactor core with fresh oxide fuel"
"An optimisation study for the safety and performance parameters of a 3600 MWth sodium-cooled fast reactor"
R. Stainsby, J.C. Garnier, P. Guedeney, K. Mikityuk, T. Mizuno, C. Poette, M. Pouchon, M. Rini, J. Somers, E. Touron.
"The Generation IV Gas-cooled Fast Reactor"
A. Chenu, K. Mikityuk, R. Adams and R. Chawla.
"TRACE Analysis of PHENIX Core Response to an Increase of the Core Inlet Sodium Temperature"
J. Krepel, J. Saliba, K. Mikityuk, R. Chawla.
"Comparison of safety related parameters in the equilibrium closed cycle for Generation-IV fast reactors"
C. Fiorina, F. Franceschini, J. Krepel, K. Mikityuk.
"Comparative Analysis of Uranium and Thorium Fuel Cycles in a Lead-Cooled Fast Reactor from the Perspective of Safety and Waste Management"
M. Pouchon, B. Niceno, and J. Křepel.
"Innovate Pin Design for Sphere-Pac Fuel in Sodium Cooled Fast Reactors"
K. Yancey, K. Mikityuk, J. Krepel, A. Chenu.
"Development and Application of a Comprehensive Model of a Lead-cooled Fast Reactor Using the FAST Code System"
J. Krepel, S. Pelloni, S. Pilarski, K. Mikityuk.
"Comparison of equilibrium closed cycles for GIV reactors by means of the EQL3D procedure"
"A review of correlations to model the pressure drop in sodium boiling in tubular geometry"
"A coupled thermal-hydraulics/ 3D kinetics TRACE/PARCS Model of the 3600 MW Gen-IV Sodium-cooled Fast Reactor: benchmark against ERANOS model"
K. Sun J. Krepel, K. Mikityuk, R. Chawla.
G. Girardin, R. Chawla, A. Epiney and K. Mikityuk.
"Neutronic analysis of water-steam injection accidents and its validation using Monte Carlo calculations for Generation IV Gas-cooled Fast Reactors"
"MCNPX Simulation of the BN-600 Fast-spectrum Core Mock-up at BFS-2 Zero-power Facility"
A. Rineiski, G. Rimpault, G. Glinatsis, N. Messaoudi, S. Pelloni, A. Schwenk-Ferrero, M. Carmen Vicente.
"Decay Heat Benchmark for Uranium-Free Fuels with Minor Actinides"
S. Pelloni, K. Mikityuk, A. Epiney.
"A new cross-section generation model in the FAST code system and its application to the Gen-IV Gas-cooled Fast Reactor"
Proceedings of International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C 2009), May 3-7, 2009, Saratoga Springs, New York, USA.
J. Krepel, K. Mikityuk, K. Sun, G. Rimpault.
"SFR equilibrium cycle analysis with the EQL3D procedure"
Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP-09), May 10-14, 2009, Shinjuku Tokyo, Japan.
J. Krepel, M. Sarotto, K. Mikityuk, C. Artioli.
"EFIT fuel cycle analysis with the EQL3D procedure"
C. Poette, J.Y. Malo, V. Brun-Magaud, F. Morin, I. Dor, B. Mathieu, H. Duhamel, R. Stainsby, K. Mikityuk.
"GFR Demonstrator ALLEGRO Design Status"
"Gas-cooled fast reactor: studies on safety enhancement"
Proceedings of 3rd ENEN PhD Event: International Youth Conference on Energetics, June 5, 2009. Budapest, Hungary.
"ESFR -- analysis of sustainable fuel cycle"
Proceedings of Seventh European Commission conference on Euratom research and training in reactor systems (FISA 2009), June 22-24, 2009, Prague, Czech Republic.
G. Girardin, D. Blanchet, K. Mikityuk, G. Rimpault and R. Chawla.
"Three-dimensional core behaviour analysis of the Gas-cooled Fast Reactor (GFR) due to control assembly withdrawal accidents"
Proceedings of International Conference on Nuclear Engineering (ICONE-17), July 12-16, 2009. Brussels, Belgium.
"Modelling of Sodium Two-phase Flow with the TRACE Code"
C. Poette, V. Brun-Magaud, F. Morin, J.F. Pignatel, R. Stainsby, K. Mikityuk.
"ALLEGRO: The European Gas Fast Reactor Demonstrator Project"
P. Anzieu, R. Stainsby, K. Mikityuk.
"Gas-cooled fast reactor (GFR): overview and perspectives"
Proceedings of GIF Symposium-2009, September 9-10, 2009, Paris, France.
A. Epiney, K. Mikityuk, N. Alpy, D. Haubensack.
"Preliminary design of a Brayton cycle for an autonomous decay heat removal in the Gas-cooled Fast Reactor"
Proceedings of International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-2009), September 27 - October 2, 2009. Kanazawa, Japan.
"Heavy gas injection in the Generation IV Gas-cooled Fast Reactor to improve decay heat removal under depressurized conditions"
"One- and two-dimensional analysis of sodium boiling under loss-of-flow conditions in a pin bundle with the TRACE code"
"Review of the recent FAST project activities related to Gen-IV fast reactors"
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009. Kyoto, Japan.
Proceedings of International Conference GLOBAL 2009. "The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives". September 6-11, 2009. Paris, France.
D. Blanchet, S. Pelloni, P. Coddington, K. Mikityuk.
"Analysis of reactivity insertion transients in the ETDR -- a small Gas Cooled Fast Reactor"
P. Dumaz, A. Epiney, N. Alpy, P. Broxtermann, J. Malo, A. Tosello.
"Studies of Unprotected Transients and Alternative Decay Heat Removal System for the Gas Cooled Fast Reactor (GFR)"
A. Epiney, P. Coddington, K. Mikityuk, R. Chawla.
"New Analysis of the EIR GFR Thermal-hydraulic Experiments"
A. Epiney, P. Dumaz, P. Coddington, K. Mikityuk, R. Chawla.
"Comparative transient analysis of the 2400MWth GFR with the TRACE and CATHARE codes"
G. Girardin, K. Mikityuk, P. Coddington, R. Chawla.
"A 3D full-core coupled thermal-hydraulics/kinetics TRACE/PARCS model of the 2400 MWth generation IV gas-cooled fast reactor"
"Equilibrium cycle analysis of a gas cooled fast reactor with the EQL3D procedure"
S. Pelloni, J. Krepel, K. Mikityuk.
"EQL3D: Methodology for simulation of equilibrium cycle for advanced fast reactors"
"GFR transient analysis employing a 2D thermomechanical model for the plate-type fuel"
C. Poette, V. Brun-Magaud, F. Morin, I. Dor, J.F. Pignatela, F. Bertrand, R. Stainsby, S. Pelloni, D. Every, D. Da Cruz.
"ETDR, The European Union’s Experimental Gas-Cooled Fast Reactor Project"
G. Girardin, G. Rimpault, P. Coddington, R. Chawla.
"Control Rod Shadowing and Anti-shadowing Effects in a Large Gas-cooled Fast Reactor"
"A 2D Transient Model for Gas-Cooled Fast Reactor Plate-Type Fuel"
E. Bubelis, D. Castelliti, P. Coddington, I. Dor, C. Fouillet, E. de Geus, T.D. Marshall, W. van Rooijen, M. Schikorr, R. Stainsby.
"A GFR benchmark comparison of transient analysis codes based on the ETDR concept"
S. Pelloni, E. Bubelis and P. Coddington.
"Steady-State and Transient Neutronic and Thermal-hydraulic Analysis of ETDR using the FAST code system"
D. Blanchet, K. Mikityuk, P. Coddington and R. Chawla.
"An Uncertainty Assessment Methodology for Materials Behaviour in Advanced Fast Reactors"
C. Mitchell, M. McDermott, K. Peers, C. Poette, P. Coddington, J. Somers.
"Gas Cooled Fast Reactor GCFR"
C. Mitchell, C. Poette, K. Peers, P. Coddington, J. Somers, G. Van-Goethem.
"GCFR: The European Union's Gas Cooled Fast Reactor Project"
E. Bubelis, P. Coddington, W. Leung.
"Pre-Test Analysis of the MEGAPIE Spallation Source Target Cooling Loop Using the TRAC/AAA Code"
P. Petkevich, K. Mikityuk, P. Coddington, S. Pelloni, R. Chawla.
"Comparative Transient Analysis of a Gas-cooled Fast Reactors for Different Fuel Types"
G. Girardin, S. Pelloni, P. Coddington, R. Chawla.
"Comparative Analysis of the Reference GCFR-PROTEUS MOX Lattice with MCNPX-2.5e and ERANOS-2.0 in Conjunction with Modern Nuclear Data Libraries"
D. Da Cruz, A. Hogenbirk, J, Bosq, G. Rimpault, G. Prulhiere, P. Morris, S. Pelloni.
"Neutronic Benchmark on the 2400 MW Gas-cooled Fast Reactor Design"
A. Epiney, S. Pelloni, P. Coddington, R. Chawla.
"Comparative Analysis for the Initial Cycle of Two Generation IV GCFR Cores (600 MWth) Operating with Innovative CERCER Type Carbide Fuel"
K. Mikityuk, S. Pelloni, P. Coddington.
"Development of an Advanced Code System for Fast-Reactor Transient Analysis"
"Verification of Reactor Dynamics Calculations Using the Coupled Code System Fast"
"Comparative Study of the Transient Behaviour of the 80MWth LBE- and Gas-cooled XADS using TRAC/AAA"
P. Coddington, K. Mikityuk, M. Schikorr, W. Maschek, B. Sehgal, J. Champigny, L. Mansani, P. Meloni, H. Wider.
"Safety Analysis of the EU-PDS-XADS Designs"
P. Coddington, K. Mikityuk, R. Chawla.
"Comparative Transient Analysis of Pb/Bi and Gas Cooled XADS Concepts"
K. Mikityuk, P.Coddington, R. Chawla.
"TRAC-M/AAA Code Assessment for Transient Analysis of Pb-Bi Cooled Fast-Spectrum Reactor Systems"
"PDS-XADS LBE and Gas-Cooled Concepts: Neutronic Parameters Comparison"
M. Plaschy, S. Pelloni, P. Coddington, R. Chawla, G. Rimpault, F. Mellier.
"Numerical Comparisons between Neutronic Characteristics of MUSE4 Configurations and XADS-type Models"
"The literature survey for the “Feasibility and plausibility of innovative reactor concepts in an European electricity supply environment” project"
"Thermal-hydraulic simulations of selected tests using CATHARE and TRACE"
"Progress report of "Feasibility and plausibility of innovative reactor concepts in an European electricity supply environment" project"
"Simulation of ULOF using ID TRACE/FRED with 0D kinetics"
"ASTRID thermal-hydraulic analysis using TRACE"
"ASTRID primary circuit thermal-hydraulic model using TRACE/FRED with 0D kinetics"
S. Bortot, K. Mikityuk, et.al.
"Review of methods, tools and databases used for core safety analysis"
"Evaluation of the ASTRID core safety coefficients"
"Serpent 2 input deck for ASTRID with a short description"
"D1.5 Results of neutronics analysis of the CFV core at EOC using Serpent 2"
"Thermal-hydraulic assessment of the ETDR core"
"OECD Halden Reactor Project Technical Visit and Data Analysis"
"Selection of a representative set of initiating events relevant to the safety issues"
"Reactivity Coefficients and Kinetics data for optimized oxide ESFR core proposed by SP2.1.3.D1"
"Reference GFR 2400 MWth: Nuclear data uncertainty analysis on the basis of COMMARA-2.0 covariances"
"User manual of the PSI extended TRACE code for sodium boiling simulation and technical advices for further developments"
"MPTVOID: An ERANOS procedure for generating regional void reactivity maps by means of perturbation theory"
"Reference GFR 2400 MWth: New nuclear data uncertainty analysis for updated core specifications"
"Reference GFR 2400 MWth: Updated core specifications and new neutronics characterization"
"Reference GFR 2400 MWth: Nuclear data uncertainty analysis"
"Reference GFR 2400 MWth: core specifications and neutronics characterization"
"Nuclear data uncertainty analysis for the Sodium Fast Reactor oxide core with its fresh fuel composition"
"Decomposition of safety related parameters for the sodium-cooled fast reactor"
"FAST code system: Documentation of Edition July 1, 2009 with a new cross-section generation model"
"Assessment of the MA burning capability of the ELSY oxide core by means of equilibrium method"
"Transient analysis for the 2400MWth GCFR: Comparison between the "0604"; and "F" core designs with the TRACE and CATHARE codes"
"GCFR Loop experiments at EIR with different gases"
"A Benchmark Comparison of Transient Analysis Codes: GCFR-STREP DEL.21"
"Neutronic and Thermal-Hydraulic Analysis of the ETDR Start-up Core"
"Post-Test Analysis of Transients Recorded at the MEGAPIE Test Facility (MITS) using the TRAC/AAA Code"
"TRAC/AAA analysis of the MEGAPie reference accident"
"Pre-Test Analysis of the Possible Transients for the MEGAPIE Facility Using the TRAC/AAA Code"
"Benchmark Specification for the Transient Analysis Codes: GCFR-STREP DEL.7"
"Analysis of ECCO/MCNPX Cell Calculation with Modern Nuclear Data Libraries for the Reference GCFR-PROTEUS MOX Cell"
"Description of Transient Codes for GFR Analysis and their Validation: GCFR-STREP DEL.6"
"A Control Rod Design for the 2400 MWth Gas-cooled Fast Reactor"
"Enhancement of the PARCS, TRAC/AAA and ERANOS Codes for use within the FAST Code System"
"Review of the GCFR-PROTEUS Experimental Programme"
"Fuel and cladding material properties for advanced Gas Cooled Fast Reactors (GFR)"
"Post-Test Analysis of the Transient Experiments Performed in the Tall Test Facility Using the TRAC/AAA Code"
"Transient Analysis of the 80 MW Helium Cooled Experimental Accelerator-Driven System Using the TRAC/AAA Code"
"UPDEDLMILIEU: A new ERANOS procedure LU"
"Transient analysis of the 80 MW Pb-Bi cooled Experimental Accelerator-Driven System using the TRAC/AAA code"
"Modifications made in the TRAC-M/AAA code, including introduction of the FRED fuel rod model"
"Results of ADS beam trip benchmark calculations with the TRAC-M and LOOP2 codes"
J. Krepel, S. Nichenko, B. Hombourger, A. Pautz, H.-M. Prasser, Chapter title: Switzerland, in the book: Molten Salt Reactors and Thorium Energy, ISBN: 978-0-08-101126-3, 2017.

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