20032020
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Research Output 2003 2020

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Conference 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

Sensitivity analysis
Fluids

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

Calibration
Uncertainty

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

Hydraulics
Hot Temperature

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

Uncertainty

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

Uncertainty

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

Void fraction
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., 2016, Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society, Vol. 5. p. 3130-3139 10 p.

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

boiling water reactors
Boiling water reactors
constrictions
damage
Flow rate
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

Fluxes

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

Neutron Transport
accidents
Accidents
Coating
coatings

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

recommendations
Nozzles
Water
nozzles
Air

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

boiling water reactors
Catastrophe
Reactor
Decay
Cusp

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

light water reactors
oscillations
Light water reactors
hydraulics
specifications

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

Hu, G., Kozlowski, T. & Brooks, C., 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, Vol. 5. p. 3768-3778 11 p.

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

boiling
Boiling liquids
heat transfer
maximum likelihood estimates
Experiments
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

Monte Carlo methods
Physics
Hydraulics
Feedback
Hot Temperature

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

Limiters
Nuclear industry
Fluids
Nuclear reactors
Two phase flow

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

Light water reactors
Accidents
Coatings
Moderators
Nuclear fuels
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

Accidents
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

Neutrons
Hydraulics
Kinetics
Hot Temperature
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

boiling water reactors
Boiling water reactors
sensitivity
predictions
hydraulics
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

Pressure vessels
Reactor shutdowns
Reactor cores
Water levels
Cooling systems

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

control rods
Control rods
retarding
reactors
hydraulics

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

Hydraulic models
Pressure vessels
Coolants
Steam piping systems
Nuclear power plants

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

Computational fluid dynamics
Accidents
Fluids
Fluid dynamics
Two phase flow

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

Codes (standards)
accidents
hydraulics
safety
Accidents
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

evaluation
predictions
hydraulics
Hydraulics
two phase flow

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

Void fraction
Pressure drop
Boundary conditions
pressure drop
bundles
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

Physics
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

Reactor cores
Simulators
Neural networks
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

Kinetics
Plutonium
Transient analysis
Power plants