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Research Output

Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance

Rose, M., Downar, T. J., Wu, X. & Kozlowski, T., Jan 1 2015, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015. American Nuclear Society, p. 2334-2344 11 p. (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015; vol. 3).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Evaluation of coupled codes RELAP5/PARCS capability for BWR global stability prediction

Kozlowski, T., Roshan, S. & Dinh, T. N., Dec 1 2007, Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Gaussian Process–Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark

Wang, C., Wu, X. & Kozlowski, T., Feb 1 2019, In : Nuclear Science and Engineering. 193, 1-2, p. 100-114 15 p.

Research output: Contribution to journalArticle

Implicit second-order scheme for steady-state thermal-hydraulic simulations

Hu, G. & Kozlowski, T., Jan 1 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 1165-1168 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Implicit second-order scheme for steady-state thermal-hydraulic simulations

Hu, G. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 1165-1168 4 p.

Research output: Contribution to journalConference article

Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code

Miglierini, B. & Kozlowski, T., Sep 15 2020, In : Annals of Nuclear Energy. 145, 107598.

Research output: Contribution to journalArticle

Inverse uncertainty quantification by hierarchical Bayesian inference for TRACE physical model parameters based on BFBT benchmark

Wang, C., Wu, X. & Kozlowski, T., Jan 1 2019, p. 4795-4807. 13 p.

Research output: Contribution to conferencePaper

Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark data

Hu, G. & Kozlowski, T., Oct 1 2016, In : Annals of Nuclear Energy. 96, p. 197-203 7 p.

Research output: Contribution to journalArticle

Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark with investigation of measurement bias

Borowiec, K. & Kozlowski, T., Jan 1 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 437-440 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Inverse uncertainty quantification of TRACE physical model parameters using sparse gird stochastic collocation surrogate model

Wu, X., Mui, T., Hu, G., Meidani, H. & Kozlowski, T., Aug 1 2017, In : Nuclear Engineering and Design. 319, p. 185-200 16 p.

Research output: Contribution to journalArticle

Inverse uncertainty quantification of trace physical model parameters with model discrepancy

Wu, X. & Kozlowski, T., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 1757-1760 4 p.

Research output: Contribution to journalConference article

Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory

Wu, X., Kozlowski, T., Meidani, H. & Shirvan, K., Aug 15 2018, In : Nuclear Engineering and Design. 335, p. 339-355 17 p.

Research output: Contribution to journalArticle

Investigation of VVER-1000 rod ejection accident according to the Phenomenon Identification and Ranking Tables for PWR

Miglierini, B. & Kozlowski, T., Sep 2018, In : Progress in Nuclear Energy. 108, p. 438-444 7 p.

Research output: Contribution to journalArticle

Investigation of Wilks’ method for uncertainty quantification of trace model for BWR spray cooling

Mui, T. & Kozlowski, T., Jan 1 2017.

Research output: Contribution to conferencePaper

Kriging-based inverse uncertainty quantification of BISON fission gas release model

Wu, X. & Kozlowski, T., Jan 1 2017, In : Transactions of the American Nuclear Society. 116, p. 629-632 4 p.

Research output: Contribution to journalConference article

Loss of coolant accident analysis under restriction of reverse flow

Radaideh, M. I., Kozlowski, T. & Farawila, Y. M., Sep 2019, In : Nuclear Engineering and Technology. 51, 6, p. 1532-1539 8 p.

Research output: Contribution to journalArticle

Open Access

Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident

Lee, D., Kozlowski, T. & Downar, T. J., Mar 2015, In : Annals of Nuclear Energy. 77, p. 94-100 7 p.

Research output: Contribution to journalArticle

Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework

Avramova, M., Ivanov, K., Kozlowski, T., Pasichnyk, I., Zwermann, W., Velkov, K., Royer, E., Yamaji, A. & Gulliford, J., Jul 28 2015, In : Annals of Nuclear Energy. 84, p. 178-196 19 p.

Research output: Contribution to journalArticle

Multi-physics coupled code reactor analysis with the U.S. NRC code system TRACE/PARCS

Xu, Y., Downar, T., Ward, A., Kozlowski, T. & Ivanov, K., Dec 1 2006, PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics. (PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics; vol. 2006).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins

Wu, X., Kozlowski, T. & Heuser, B. J., Jan 1 2014, International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, p. 159-166 8 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions

Wu, X., Kozlowski, T. & Hales, J. D., May 6 2015, In : Annals of Nuclear Energy. 85, p. 763-775 13 p.

Research output: Contribution to journalArticle

OECD/NEA and U.S. NRC PWR MOX/UO 2 core transient benchmark

Kozlowski, T., Cotton, C. A., Downar, T. J. & Lee, R., Dec 1 2003, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 368-371 4 p. (Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

On the connection between sensitivity and identifiability for inverse uncertainty quantification

Wu, X., Shirvan, K. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 411-414 4 p.

Research output: Contribution to journalConference article

On the connection between sensitivity and identifiability for inverse uncertainty quantification

Wu, X., Shirvan, K. & Kozlowski, T., Jan 1 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 411-414 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties

Radaideh, M. I., Price, D. & Kozlowski, T., Jan 1 2019, (Accepted/In press) In : Nuclear Engineering and Technology.

Research output: Contribution to journalArticle

Open Access

Optimal Krylov Preconditioning for Solution of the Multi-group, SP 3 Neutron Transport Equations

Kozlowski, T., Downar, T. J. & Lewis, E. E., 2003, In : Transactions of the American Nuclear Society. 89, p. 498 1 p.

Research output: Contribution to journalArticle

Physics analysis of coolant voiding in the ACR-700 lattice

Cotton, C. A., Lee, D., Kozlowski, T., Downar, T. J., Yang, W. S. & Carlson, D. E., Dec 1 2005, In : Transactions of the American Nuclear Society. 92, p. 685-687 3 p.

Research output: Contribution to journalConference article

Pin2Perform: A framework for consistent fuel performance calculations

O'Grady, D., Price, D. R., Kozlowski, T., Martin, J. F. & Hill, I., Jan 1 2020, p. 445-449. 5 p.

Research output: Contribution to conferencePaper

Predicting actual reactor conditions: Why timedomain simulation is necessary for BWR stability

Kozlowski, T., Peltonen, J., Gajev, I., Phung, V. A. & Roshan, S., 2013, In : International Journal of Nuclear Energy Science and Technology. 7, 4, p. 319-342 24 p.

Research output: Contribution to journalArticle

Qualification of the 3D Thermal Hydraulics Model of the Code System TRACE Based on plant data

Sánchez, V. H., Jäger, W. & Kozlowski, T., Sep 26 2008, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". p. 1084-1092 9 p. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; vol. 2).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Qualification of the RELAP5/PARCS code for bwr stability events prediction

Kozlowski, T. & Peltonen, J., Apr 2011, In : Nuclear Technology. 174, 1, p. 51-63 13 p.

Research output: Contribution to journalArticle

Recommendations on two-phase critical non-flashing flows calculations in one-dimensional system code RELAP5

Sokolowski, L. & Kozlowski, T., Jan 1 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 2117-2130 14 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 3).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

RELAP5 and TRACE codes comparison and validation under steady-state and transient conditions on the basis of NUPEC data

Suchoszek, J., Cadinu, F., Kozlowski, T. & Dinh, T. N., Dec 1 2007, Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

RELAP5 performance in predicting critical power in a BWR fuel bundle

Cadinu, F., Kozlowski, T. & Dinh, T. N., Dec 21 2006, In : Transactions of the American Nuclear Society. 95, p. 650-651 2 p.

Research output: Contribution to journalConference article

Relating system-to-CFD coupled code analyses to theoretical framework of a multiscale method

Cadinu, F., Kozlowski, T. & Dinh, T. N., Sep 26 2008, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". p. 2959-2967 9 p. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; vol. 5).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Review of multi-physics temporal coupling methods for analysis of nuclear reactors

Zerkak, O., Kozlowski, T. & Gajev, I., Jul 28 2015, In : Annals of Nuclear Energy. 84, p. 225-233 9 p.

Research output: Contribution to journalArticle

Review of Progress in Coated Fuel Particle Performance Analysis

Baghdasaryan, N. & Kozlowski, T., Mar 3 2020, In : Nuclear Science and Engineering. 194, 3, p. 169-180 12 p.

Research output: Contribution to journalReview article

Sensitivity analysis of input uncertain parameters on BWR stability using TRACE/PARCS

Gajev, I., Ma, W. & Kozlowski, T., May 1 2014, In : Annals of Nuclear Energy. 67, p. 49-58 10 p.

Research output: Contribution to journalArticle

Sensitivity and uncertainty of OECD benchmark ringhals-1 TRACE/PARCS stability prediction

Gajev, I., Kozlowski, T., Xu, Y. & Downar, T., Dec 2012, In : Nuclear Technology. 180, 3, p. 383-398 16 p.

Research output: Contribution to journalArticle

Sensitivity and uncertainty of the neutronic parameters of BWR ringhals-1 TRACE/PARCS stability prediction

Gajev, I., Kozlowski, T., Xu, Y. & Downar, T., Dec 1 2010, International Conference on the Physics of Reactors 2010, PHYSOR 2010. p. 3320-3331 12 p. (International Conference on the Physics of Reactors 2010, PHYSOR 2010; vol. 4).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Sensitivity studies for the exercise I-1 of the OECD/UAM benchmark

Canuti, E., Petruzzi, A., D'Auria, F. & Kozlowski, T., 2012, In : Science and Technology of Nuclear Installations. 2012, 817185.

Research output: Contribution to journalArticle