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Research Output

Shapley effect application for variance-based sensitivity analysis of the few-group cross-sections

Radaideh, M. I., Surani, S., O'Grady, D. & Kozlowski, T., Jul 2019, In : Annals of Nuclear Energy. 129, p. 264-279 16 p.

Research output: Contribution to journalArticle

Simulation of PWR load follow operation using VERA-CS

O'Grady, D., Mui, T. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 119, p. 1065-1068 4 p.

Research output: Contribution to journalConference article

Simulation of two-phase flow instability in CIRCUS facility using RELAP5

Phung, V. A., Kozlowski, T., Kudinov, P. & Rohde, M., Dec 1 2008, In : Transactions of the American Nuclear Society. 99, p. 813-814 2 p.

Research output: Contribution to journalConference article

Space-time convergence analysis on BWR stability using TRACE/PARCS

Gajev, I., Ma, W. & Kozlowski, T., Jan 1 2013, In : Annals of Nuclear Energy. 51, p. 295-306 12 p.

Research output: Contribution to journalArticle

Space-time convergence study based on OECD Ringhals-1 Stability Benchmark

Gajev, I., Kozlowski, T. & Ma, W., 2012, In : Transactions of the American Nuclear Society. 106, p. 984-987 4 p.

Research output: Contribution to journalArticle

Spatial coupling for BWR stability analysis

Kozlowski, T., Peltonen, J. & Dinh, T. N., Nov 7 2008, In : Transactions of the American Nuclear Society. 98, p. 603-605 3 p.

Research output: Contribution to journalConference article

Spatial coupling for coupled code safety analysis of BWR design-basis accidents

Peltonen, J., Kozlowski, T. & Dinh, T. N., Dec 1 2008, International Conference on the Physics of Reactors 2008, PHYSOR 08. p. 1313-1320 8 p. (International Conference on the Physics of Reactors 2008, PHYSOR 08; vol. 2).

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

Surrogate modeling of advanced computer simulations using deep Gaussian processes

Radaideh, M. I. & Kozlowski, T., Mar 2020, In : Reliability Engineering and System Safety. 195, 106731.

Research output: Contribution to journalArticle

The stability of boiling water reactors as a catastrophe phenomenon

Pázsit, I., Dykin, V., Konno, H. & 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. 763-774 12 p. (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015; vol. 1).

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

The use of an Artificial Neural Network for on-line prediction of Pin-Cell Discontinuity Factors in PARCS

Kozlowski, T., Lee, D. & Downar, T. J., Dec 1 2004, Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. p. 613-623 11 p. (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

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

TRACE/PARCS analysis of the OECD/NEA Oskarshamn-2 BWR stability benchmark

Kozlowski, T., Downar, T., Xu, Y., Wysocki, A., Ivanov, K., Magedanz, J., Hardgrove, M., March-Leuba, J., Hudson, N. & Woodyatt, D., Dec 6 2012, International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics. p. 1996-2010 15 p. (International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics; vol. 3).

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

Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark

Dokhane, A., Zerkak, O., Ferroukhi, H., Gajev, I., Judd, J. & Kozlowski, T., Jan 1 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 4757-4770 14 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 6).

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

TRACE code validation against ISP-15 FIX-II LOCA blowdown and pump trip heat experiment

Sokolowski, L. & Kozlowski, T., 2011, In : Transactions of the American Nuclear Society. 104, p. 1008-1010 3 p.

Research output: Contribution to journalArticle

Trace V5 code application dvi line break loca using atlas facility

Veronese, F. & Kozlowsk, T., Oct 1 2012, In : Nuclear Engineering and Technology. 44, 7, p. 719-726 8 p.

Research output: Contribution to journalArticle

Uncertainty analysis of rod ejection accident in VVER-1000 reactor

Miglierini, B., Kozlowski, T. & Kopecek, V., Oct 2019, In : Annals of Nuclear Energy. 132, p. 628-635 8 p.

Research output: Contribution to journalReview article

Uncertainty quantification for coupled Monte Carlo and thermal-hydraulics codes

Wu, X. & Kozlowski, T., Jan 1 2014, In : Transactions of the American Nuclear Society. 110, p. 189-191 3 p.

Research output: Contribution to journalConference article

Uncertainty quantification for steady-state PSBT benchmark using surrogate models

Borowiec, K., Wang, C., Kozlowski, T. & Brooks, C. S., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 119-122 4 p.

Research output: Contribution to journalConference article

Uncertainty quantification of model-form and predictive uncertainties in nuclear codes using Bayesian framework

Radaideh, M. I., Borowiec, K. & Kozlowski, T., Jan 1 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, p. 2775-2784 10 p. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

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

Uncertainty quantification of trace wall heat transfer modeling in subcooled boiling using bfbt experiments

Hu, G., Kozlowski, T. & Brooks, C., Jan 1 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 3768-3778 11 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 5).

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

Validating trace void fraction predictive capability using the quantitative area validation metric

Wu, X., Shirvan, K. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 423-426 4 p.

Research output: Contribution to journalConference article

Validating TRACE void fraction predictive capability using the quantitative area validation metric

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. 423-426 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

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

Validation and Uncertainty Quantification for Two-Phase Natural Circulation Flows Using TRACE Code

Borowiec, K., Kozlowski, T. & Brooks, C. S., Feb 13 2020, (Accepted/In press) In : Nuclear Science and Engineering.

Research output: Contribution to journalArticle

Validation of a pin-based screening methodology for the investigation of pellet-clad interaction during load-follow operation

O'Grady, D. & Kozlowski, T., Jan 1 2020, p. 795-803. 9 p.

Research output: Contribution to conferencePaper