Publications by Jan Dufek
Peer reviewed
Articles
[1]
Y. M. Chan and J. Dufek, "A deep-learning representation of multi-group cross sections in lattice calculations," Annals of Nuclear Energy, vol. 195, 2024.
[2]
Y. M. Chan and J. Dufek, "Representation of multi-group cross section libraries and flux spectra for PWR materials with deep neural networks for lattice calculations," Annals of Nuclear Energy, vol. 208, 2024.
[3]
I. Mickus and J. Dufek, "Does neutron clustering affect tally errors in Monte Carlo criticality calculations?," Annals of Nuclear Energy, vol. 155, 2021.
[4]
J. Dufek and I. Mickus, "Optimal time step length and statistics in Monte Carlo burnup simulations," Annals of Nuclear Energy, vol. 139, 2020.
[5]
I. Mickus, J. A. Roberts and J. Dufek, "Stochastic-deterministic response matrix method for reactor transients," Annals of Nuclear Energy, vol. 140, pp. 107103, 2020.
[6]
I. Mickus and J. Dufek, "Optimal neutron population growth in accelerated Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 117, pp. 297-304, 2018.
[7]
B. Olsen and J. Dufek, "Fission source sampling in coupled Monte Carlo simulations," Kerntechnik (1987), vol. 82, no. 2, pp. 206-209, 2017.
[8]
B. Olsen and J. Dufek, "Stabilization effect of fission source in coupled Monte Carlo simulations," Nuclear engineering and technology : an international journal of the Korean Nuclear Society, vol. 49, no. 5, pp. 1095-1099, 2017.
[9]
J. Dufek and G. Holst, "Correlation of errors in the Monte Carlo fission source and the fission matrix fundamental-mode eigenvector," Annals of Nuclear Energy, vol. 94, pp. 415-421, 2016.
[10]
J. Dufek and K. Tuttelberg, "Monte Carlo criticality calculations accelerated by a growing neutron population," Annals of Nuclear Energy, vol. 94, pp. 16-21, 2016.
[11]
K. Tuttelberg and J. Dufek, "Neutron batch size optimisation methodology for Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 75, pp. 620-626, 2015.
[12]
I. Mickus, J. Dufek and K. Tuttelberg, "PERFORMANCE OF THE EXPLICIT EULER AND PREDICTOR-CORRECTOR-BASED COUPLING SCHEMES IN MONTE CARLO BURNUP CALCULATIONS OF FAST REACTORS," Nuclear Technology, vol. 191, no. 2, pp. 193-198, 2015.
[13]
J. Dufek and J. Eduard Hoogenboom, "Description of a stable scheme for steady-state coupled Monte Carlo-thermal-hydraulic calculations," Annals of Nuclear Energy, vol. 68, pp. 1-3, 2014.
[14]
A. Riber Marklund and J. Dufek, "Development and comparison of spectral methods for passive acoustic anomaly detection in nuclear power plants," Applied Acoustics, vol. 83, pp. 100-107, 2014.
[15]
K. Tuttelberg and J. Dufek, "Estimation of errors in the cumulative Monte Carlo fission source," Annals of Nuclear Energy, vol. 72, pp. 151-155, 2014.
[16]
J. Dufek and V. Valtavirta, "Time step length versus efficiency of Monte Carlo burnup calculations," Annals of Nuclear Energy, vol. 72, pp. 409-412, 2014.
[17]
J. Dufek and H. Anglart, "Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal-hydraulic feedback," Annals of Nuclear Energy, vol. 62, pp. 260-263, 2013.
[18]
J. Dufek et al., "Numerical stability of the predictor-corrector method in Monte Carlo burnup calculations of critical reactors," Annals of Nuclear Energy, vol. 56, pp. 34-38, 2013.
[19]
A. E. Isotalo, J. Leppänen and J. Dufek, "Preventing xenon oscillations in Monte Carlo burnup calculations by enforcing equilibrium xenon distribution," Annals of Nuclear Energy, vol. 60, pp. 78-85, 2013.
[20]
J. Dufek, D. Kotlyar and E. Shwageraus, "The stochastic implicit Euler method - A stable coupling scheme for Monte Carlo burnup calculations," Annals of Nuclear Energy, vol. 60, pp. 295-300, 2013.
[21]
J. Dufek, "Building the nodal nuclear data dependences in a many-dimensional state-variable space," Annals of Nuclear Energy, vol. 38, no. 7, pp. 1569-1577, 2011.
[22]
J. Dufek and W. Gudowski, "An efficient parallel computing scheme for Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 36, no. 8, pp. 1276-1279, 2009.
[23]
J. Dufek and W. Gudowski, "Fission matrix based Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 36, no. 8, pp. 1270-1275, 2009.
[24]
J. Dufek and E. Hoogenboom, "Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors," Nuclear science and engineering, vol. 162, no. 3, pp. 307-311, 2009.
[25]
J. Dufek and W. Gudowski, "Stability and convergence problems of the Monte Carlo fission matrix acceleration methods," Annals of Nuclear Energy, vol. 36, no. 10, pp. 1648-1651, 2009.
[26]
A. Ålander, J. Dufek and W. Gudowski, "From once-through nuclear fuel cycle to accelerator-driven transmutation," Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 562, no. 2, pp. 630-633, 2006.
[27]
J. Dufek and W. Gudowski, "Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors," Nuclear science and engineering, vol. 152, pp. 274-283, 2006.
Conference papers
[28]
I. Mickus, J. A. Roberts and J. Dufek, "Application of response matrix method to transient simulations of nuclear systems," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 786-793.
[29]
J. Dufek and I. Mickus, "Optimisation of Monte Carlo burnup simulations," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 804-810.
[30]
V. H. Sanchez-Espinoza et al., "The McSAFE project - High-performance Monte Carlo based methods for safety demonstration : From proof of concept to industry applications," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 943-950.
Non-peer reviewed
Theses
[31]
J. Dufek, "Development of New Monte Carlo Methods in Reactor Physics : Criticality, Non-Linear Steady-State and Burnup Problems," Doctoral thesis Stockholm : Universitetsservice US AB, Trita-FYS, 2009:20, 2009.
[32]
J. Dufek, "Advanced Monte Carlo Methods in Reactor Physics, Eigenvalue and Steady State Problems," Licentiate thesis Stockholm : KTH, Trita-FYS, 2007:40, 2007.
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2024-09-11 00:35:51