20032020
If you made any changes in Pure, your changes will be visible here soon.

Research Output 2003 2020

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

boiling water reactors
Boiling water reactors
sensitivity
predictions
Parameterization

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

Uncertainty analysis
Light water reactors
Physics
Uncertainty

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

Sensitivity analysis
Game theory
Costs
Uncertainty
Hot Temperature

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

Boiling water reactors
Economics

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

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

Computer simulation
Screening
Nuclear engineering
Hydraulic fluids
Uncertainty analysis
Computational Science
Engineering
Students
Computing
Integrate

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

Loss of coolant accidents
Pumps
Experiments
Hot Temperature
Test facilities
Cooling
Experiments
Temperature
Uncertainty

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

Test facilities
Two phase flow
Accidents
Experiments
Hydraulics
Conference article

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

Hu, G. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 1169-1172 4 p.

Research output: Contribution to journalConference article

Sensitivity analysis
Fluids

A high-order numerical solver for the two-phase two-fluid six-equation model with realistic equation of state

Hu, G. & Kozlowski, T., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 1753-1756 4 p.

Research output: Contribution to journalConference article

Equations of state
Fluids

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

Two phase flow
Physics
Fluids

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

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

Neural networks

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

Transient analysis

Bayesian calibration and uncertainty quantification for trace based on PSBT benchmark

Wang, C., Wu, X., Borowiec, K. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 419-422 4 p.

Research output: Contribution to journalConference article

Calibration
Uncertainty

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

Hydraulics
Hot Temperature
Uncertainty

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

Uncertainty

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

Gases
Uncertainty

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

Uncertainty

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

Coolants
Physics

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

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

Two phase flow

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

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

Hydraulics
Hot Temperature
Uncertainty

Uncertainty quantification for steady-state PSBT benchmark using surrogate models

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

Research output: Contribution to journalConference article

Uncertainty

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

Void fraction
Conference contribution

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

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

boiling water reactors
Boiling water reactors
constrictions
damage
Flow rate

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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