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Research Output

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Conference contribution
2019

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

2018

Adjoint sensitivity analysis of the two-phase two-fluid model

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. 1169-1172 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

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

Bayesian calibration and uncertainty quantification for TRACE based on PSBT benchmark

Wang, C., Wu, X., 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. 419-422 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, 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

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

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

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

2016

Analysis of reverse flow restriction device to prevent fuel dryout damage during boiling water reactor instability

Radaideh, M. I., Kozlowski, T. & Farawila, Y. M., Jan 1 2016, Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society, p. 3130-3139 10 p. (Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century; vol. 5).

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

2015

Comparative neutronics analysis of dimple S06 benchmark

Kim, W., Park, J., Lee, D. & Kozlowski, T., Jan 1 2015, 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, p. 416-431 16 p. (5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V).

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

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

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

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

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

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

2014

Coupling of system thermal-hydraulics and monte-carlo method for a consistent thermal-hydraulics-reactor physics feedback

Wu, X. & Kozlowski, T., Jan 1 2014, International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, p. 1164-1174 11 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; vol. 2).

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

Development of accurate and stable two-phase two-fluid model solver

Abu Saleem, R. A. & Kozlowski, T., Jan 1 2014, International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, p. 1586-1594 9 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; vol. 2).

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

2013

Engineered Zircaloy cladding modifications for improved accident tolerance of LWR fuel: A summary

Heuser, B. J., Kozlowski, T. & Xu, W., Jan 1 2013, LWR Fuel Performance Meeting, Top Fuel 2013. American Nuclear Society, p. 56-58 3 p. (LWR Fuel Performance Meeting, Top Fuel 2013; vol. 1).

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

2012

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

2010

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

2008

A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant

Roshan, S. S., Ma, W., 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. 2642-2651 10 p. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; vol. 4).

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

Design of BWR instability suppression system

Kubarev, A., Kozlowski, T., Roshan, S. S. & Dinh, T. N., Dec 1 2008, International Conference on the Physics of Reactors 2008, PHYSOR 08. p. 2062-2068 7 p. (International Conference on the Physics of Reactors 2008, PHYSOR 08; vol. 3).

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

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

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

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

2007

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

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

2006

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

2004

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

2003

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