Tomasz Kozlowski

Tomasz Kozlowski
Tomasz Kozlowski
Associate Professor and Associate Head for Undergraduate Programs
(217) 333-4096
111D Talbot Laboratory
Associate Professor and Associate Head For Undergraduate Programs
(217) 333-4096
111D Talbot Laboratory

For more information

Education

  • Royal Institute of Technology, Docent habilitation, Nuclear Power Safety, 2011
  • Purdue University, Ph.D., Nuclear Engineering, 2005
  • Purdue University, M.S., Nuclear Engineering, 2004
  • Purdue University, B.S., Nuclear Engineering, 2000

Academic Positions

  • 2020-present, Associate Head for Undergraduate Programs, University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering
  • 2017-present, Associate Professor, University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma and Radiological Engineering
  • 2016-present, Associate Professor, National Centre for Nuclear Research (NCBJ)
  • 2015, Visiting Professor, Warsaw Institute of Technology
  • 2013-present, Affiliated Professor, Computational Science and Engineering, University of Illinois at Urbana-Champaign, Nuclear, Plasma, and Radiological Engineering
  • 2011-2017, Assistant Professor, University of Illinois at Urbana-Champaign, Nuclear, Plasma and Radiological Engineering
  • 2009-2011, Assistant Professor, Royal Institute of Technology, Nuclear Power Safety, Stockholm, Sweden

Research Interests

  • Multi-Physics Methods and Modeling
  • Reactor Design and Safety Analysis
  • Reactor Physics and Thermal-Hydraulics
  • Numerical Analysis and Computational Methods

Research Areas

  • Advanced Reactor Designs
  • Multi-Physics Modeling and Simulation
  • Reactor Analysis Methods
  • Reactor Physics
  • Reactor Thermal-Hydraulics
  • Reactor Transient and Accident Analysis
  • Verification, Validation and Uncertainty Methods

Selected Articles in Journals

  • Development of a WENO-type numerical solver for two-phase two-fluid six-equation model, Hu, G. & Kozlowski, T., Mar 2022, In: Annals of Nuclear Energy. 167, 108840.
  • A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes, Wu, X., Xie, Z., Alsafadi, F. & Kozlowski, T., Dec 1 2021, In: Nuclear Engineering and Design. 384, 111460.
  • A multiscale approach to analyze the effect of radial void fraction distributions on BWR neutronic lattice parameters, Price, D. & Kozlowski, T., Mar 2021, In: Annals of Nuclear Energy. 152, 107988.
  • Comprehensive framework for data-driven model form discovery of the closure laws in thermal-hydraulics codes, Borowiec, K., Wysocki, A. J. & Kozlowski, T., May 2021, In: International Journal of Heat and Mass Transfer. 170, 120976.
  • Pressure buildup analysis of TRISO-coated fuel particles, Baghdasaryan, N. & Kozlowski, T., Aug 15 2021, In: Nuclear Engineering and Design. 380, 111279.
  • Analyzing nuclear reactor simulation data and uncertainty with the group method of data handling, Radaideh, M. I. & Kozlowski, T., Feb 2020, In: Nuclear Engineering and Technology. 52, 2, p. 287-295 9 p.
  • A possible application of catastrophe theory to boiling water reactor instability, Pázsit, I., Dykin, V., Konno, H. & Kozlowski, T., Jan 2020, In: Progress in Nuclear Energy. 118, 103054.
  • Application of deep neural networks for high-dimensional large BWR core neutronics, Abu Saleem, R., Radaideh, M. I. & Kozlowski, T., Dec 2020, In: Nuclear Engineering and Technology. 52, 12, p. 2709-2716 8 p.
  • Design optimization under uncertainty of hybrid fuel cell energy systems for power generation and cooling purposes, Radaideh, M. I. & Kozlowski, T., Jan 13 2020, In: International Journal of Hydrogen Energy. 45, 3, p. 2224-2243 20 p.
  • Development and assessment of adjoint sensitivity analysis method for transient two-phase flow simulations, Hu, G. & Kozlowski, T., Nov 2020, In: Annals of Nuclear Energy. 147, 107731.

Journal Editorships

  • Associate Editor for "Nuclear Technology", since 2021

Recent Courses Taught

  • NPRE 100 - Orientation to NPRE
  • NPRE 200 - Mathematics for NPRE
  • NPRE 247 - Modeling Nuclear Energy System
  • NPRE 455 - Neutron Diffusion & Transport
  • NPRE 458 - Design in NPRE
  • NPRE 558 - Advanced Design in NPRE
  • NPRE 595 - Student Research Seminar