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Research Output

2003

Application of Artificial Neural Network to Online Prediction of Pin-Cell Discontinuity Factor

Lee, D., Kozlowski, T., Downar, T. J. & Kim, Y., Dec 29 2003, In : Transactions of the American Nuclear Society. 89, 1 p.

Research output: Contribution to journalConference article

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

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

2004

Application of SP3 approximation to MOX transient analysis in PARCS

Lee, D., Kozlowski, T., Downar, T., Lee, C. & Lee, H. C., Dec 1 2004, In : Transactions of the American Nuclear Society. 91, p. 252-256 5 p.

Research output: Contribution to journalConference article

Consistent comparison of the codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB coupled code benchmark

Kozlowski, T., Miller, R. M., Downar, T. J., Barber, D. A. & Joo, H. G., Apr 2004, In : Nuclear Technology. 146, 1, p. 15-28 14 p.

Research output: Contribution to journalArticle

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

2005

Analysis of results for the OECD/NEA and U.S. NRC PWR MOX/UO 2 core transient benchmark

Kozlowski, T. & Downar, T. J., Dec 1 2005, In : Transactions of the American Nuclear Society. 92, p. 639-641 3 p.

Research output: Contribution to journalConference article

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

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

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

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

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

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

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

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

2011

Cell homogenization method for pin-by-pin neutron transport calculations

Kozlowski, T., Xu, Y., Downar, T. J. & Lee, D., Sep 2011, In : Nuclear Science and Engineering. 169, 1, p. 1-18 18 p.

Research output: Contribution to journalArticle

Development of effective algorithm for coupled thermal-hydraulic-neutron- kinetics analysis of reactivity transient

Peltonen, J. & Kozlowski, T., Nov 2011, In : Nuclear Technology. 176, 2, p. 195-210 16 p.

Research output: Contribution to journalArticle

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

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

2012

Analysis of interfacial forces on the physics of two-phase flow and hyperbolicity of the two-fluid model

Talpaert, A. & Kozlowski, T., Dec 1 2012, In : Transactions of the American Nuclear Society. 107, p. 1344-1346 3 p.

Research output: Contribution to journalConference article

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

Canuti, E., Petruzzi, A., D'Auria, F. & Kozlowski, T., Dec 1 2012, In : Science and Technology of Nuclear Installations. 2012, 817185.

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

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 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

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

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

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

2014

Analysis of the OECD/NRC Oskarshamn-2 BWR stability benchmark

Kozlowski, T., Wysocki, A., Gajev, I., Xu, Y., Downar, T., Ivanov, K., Magedanz, J., Hardgrove, M., March-Leuba, J., Hudson, N. & Ma, W., May 1 2014, In : Annals of Nuclear Energy. 67, p. 4-12 9 p.

Research output: Contribution to journalArticle

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

Effective spatial mapping for coupled code analysis of thermal-hydraulics/ neutron-kinetics of boiling water reactors

Peltonen, J., Ma, W. & Kozlowski, T., Jan 1 2014, In : Annals of Nuclear Energy. 63, p. 461-485 25 p.

Research output: Contribution to journalReview article

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

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

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

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

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

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