Linear Chain Method for Numerical Modelling of Burnup Systems von Cetnar, Jerzy, Stanisz, Przemyslaw, Oettingen, Mikolaj

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Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel von Oettingen, Mikołaj, Cetnar, Jerzy

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Development of a Trajectory Period Folding Method for Burnup Calculations von Stanisz, Przemysław, Oettingen, Mikołaj, Cetnar, Jerzy

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Flattening of the Power Distribution in the HTGR Core with Structured Control Rods von Gorkiewicz, Michal, Cetnar, Jerzy

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Radionuclide neutron source trajectories in the closed nuclear fuel cycle von Stanisz, Przemysław, Cetnar, Jerzy, Oettingen, Mikołaj

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Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR von Oettingen, Mikołaj, Cetnar, Jerzy

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Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR von Kępisty, Grzegorz, Cetnar, Jerzy

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Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent von Królikowski, Igor P., Cetnar, Jerzy

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THE MCB CODE FOR NUMERICAL MODELING OF FOURTH GENERATION NUCLEAR REACTORS von Mikolaj, Oettingen, Jerzy, Cetnar, Tomasz, Mirowski

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General solution of Bateman equations for nuclear transmutations von Cetnar, Jerzy

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Comparison of statistical evaluation of criticality calculations for reactors VENUS-F and ALFRED von Janczyszyn, Jerzy, Domańska, Grażyna, Cetnar, Jerzy

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Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without long-lived nuclear waste von Stanisz, Przemysław, Cetnar, Jerzy, Domańska, Grażyna

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Assessment of the control rods shadow effect in the VENUS-F core von Cetnar, Jerzy, Domańska, Grażyna, Gajda, Paweł, Janczyszyn, Jerzy

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Monte Carlo modeling of Lead-Cooled Fast Reactor in adiabatic equilibrium state von Stanisz, Przemysław, Oettingen, Mikołaj, Cetnar, Jerzy

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Validation of gadolinium burnout using PWR benchmark specification von Oettingen, Mikołaj, Cetnar, Jerzy

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Instabilities of Monte-Carlo burnup calculations for nuclear reactors—Demonstration and dependence from time step model von Kępisty, Grzegorz, Cetnar, Jerzy

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Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles von TALAMO, Alberto, GUDOWSKI, Waclaw, CETNAR, Jerzy

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Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method von Kępisty, Grzegorz, Cetnar, Jerzy, Stanisz, Przemysław

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Burnup instabilities in the full-core HTR model simulation von Kępisty, Grzegorz, Cetnar, Jerzy

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Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing von Sarotto, Massimo, Firpo, Gabriele, Kochetkov, Anatoly, Krása, Antonin, Fridman, Emil, Cetnar, Jerzy, Domanska, Grazyna

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