Tomasz Kozlowski, Ph.D

Affiliations: 
Nuclear Engineering University of Illinois, Urbana-Champaign, Urbana-Champaign, IL 
Area:
Computational Methods
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"Tomasz Kozlowski"
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Thomas J. Downar grad student 2005 Purdue (E-Tree)
 (Spatial homogenization methods for pin -by -pin neutron transport calculations.)
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Publications

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Price D, Radaideh MI, Mui T, et al. (2020) Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations Science and Technology of Nuclear Installations. 2020: 1-14
Borowiec K, Kozlowski T, Brooks CS. (2020) Validation and Uncertainty Quantification for Two-Phase Natural Circulation Flows Using TRACE Code Nuclear Science and Engineering. 194: 737-747
Radaideh MI, Kozlowski T. (2020) Surrogate modeling of advanced computer simulations using deep Gaussian processes Reliability Engineering & System Safety. 195: 106731
Pázsit I, Dykin V, Konno H, et al. (2020) A possible application of catastrophe theory to boiling water reactor instability Progress in Nuclear Energy. 118: 103054
Saleem RA, Radaideh MI, Kozlowski T. (2020) Application of deep neural networks for high-dimensional large BWR core neutronics Nuclear Engineering and Technology
Radaideh MI, Price D, Kozlowski T. (2020) On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties Nuclear Engineering and Technology. 52: 1148-1155
Radaideh MI, Kozlowski T. (2020) Analyzing nuclear reactor simulation data and uncertainty with the group method of data handling Nuclear Engineering and Technology. 52: 287-295
Radaideh MI, Radaideh MI, Kozlowski T. (2020) Design optimization under uncertainty of hybrid fuel cell energy systems for power generation and cooling purposes International Journal of Hydrogen Energy. 45: 2224-2243
Radaideh MI, Pigg C, Kozlowski T, et al. (2020) Neural-based time series forecasting of loss of coolant accidents in nuclear power plants Expert Systems With Applications. 160: 113699
Miglierini B, Kozlowski T. (2020) Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code Annals of Nuclear Energy. 145: 107598
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