20032020
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Research Output 2003 2020

Uncertainty
Hydraulics
Nuclear engineering
Uncertainty analysis
Void fraction

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

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
Statistics
Uncertainty
Nuclear engineering
Light water reactors
Void fraction

Inverse uncertainty quantification by hierarchical Bayesian inference for TRACE physical model parameters based on BFBT benchmark

Wang, C., Wu, X. & Kozlowski, T., Jan 1 2019, p. 4795-4807. 13 p.

Research output: Contribution to conferencePaper

inference
Markov chains
sampling
Sampling
Markov processes
Uncertainty Quantification
Expectation Maximization
Hydraulics
Simulation
Model Uncertainty
chaotic dynamics
Chaos theory
chaos
polynomials
reactors

Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark data

Hu, G. & Kozlowski, T., Oct 1 2016, In : Annals of Nuclear Energy. 96, p. 197-203 7 p.

Research output: Contribution to journalArticle

Void fraction
Maximum likelihood estimation
Markov processes
Uncertainty
Probability distributions

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
Uncertainty

Inverse uncertainty quantification of TRACE physical model parameters using sparse gird stochastic collocation surrogate model

Wu, X., Mui, T., Hu, G., Meidani, H. & Kozlowski, T., Aug 1 2017, In : Nuclear Engineering and Design. 319, p. 185-200 16 p.

Research output: Contribution to journalArticle

collocation
sensitivity analysis
estimates
closure law
design analysis

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

Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory

Wu, X., Kozlowski, T., Meidani, H. & Shirvan, K., Aug 15 2018, In : Nuclear Engineering and Design. 335, p. 339-355 17 p.

Research output: Contribution to journalArticle

formulations
design analysis
Bayesian analysis
nuclear reactors
prediction
Probability distributions
Uncertainty
test
Void fraction
self assessment

Investigation of VVER-1000 rod ejection accident according to the Phenomenon Identification and Ranking Tables for PWR

Miglierini, B. & Kozlowski, T., Sep 2018, In : Progress in Nuclear Energy. 108, p. 438-444 7 p.

Research output: Contribution to journalArticle

Control rods
Pressurized water reactors
ranking
accident
Reactor cores

Investigation of Wilks’ method for uncertainty quantification of trace model for BWR spray cooling

Mui, T. & Kozlowski, T., Jan 1 2016.

Research output: Contribution to conferencePaper

sprayers
licensing
Cooling
cooling
reactor safety

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
Nuclear fuels
Time series
Gases
Nuclear reactors
Principal component analysis

Loss of coolant accident analysis under restriction of reverse flow

Radaideh, M. I., Kozlowski, T. & Farawila, Y. M., Sep 2019, In : Nuclear Engineering and Technology. 51, 6, p. 1532-1539 8 p.

Research output: Contribution to journalArticle

Open Access
Loss of coolant accidents
Coolants
Temperature
Boiling water reactors
Cooling water

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

Reactor cores
Pressurized water reactors
Accidents
Core analysis
Light water reactors

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

Benchmarking
Light water reactors
Nuclear energy
Physics
Economics

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

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

Accidents
Pressurized water reactors
Fabrication
Coatings
Pressurization

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
Jacobian matrices
Eigenvalues and eigenfunctions
eigenvectors
eigenvalues
Fluids
Jacobian matrices
eigenvalue
Eigenvalues and eigenfunctions
eigenvectors
eigenvalues

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

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

On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties

Radaideh, M. I., Price, D. & Kozlowski, T., Jan 1 2019, (Accepted/In press) In : Nuclear Engineering and Technology.

Research output: Contribution to journalArticle

Open Access
Chemical analysis
Isotopes
Uncertainty
Assays
Geometry

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

Neutrons

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

Predicting actual reactor conditions: Why timedomain simulation is necessary for BWR stability

Kozlowski, T., Peltonen, J., Gajev, I., Phung, V. A. & Roshan, S., Jun 21 2013, In : International Journal of Nuclear Energy Science and Technology. 7, 4, p. 319-342 24 p.

Research output: Contribution to journalArticle

Neutrons
Hydraulics
Kinetics
Benchmarking
Numerical methods

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

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

qualifications
predictions
hydraulics
Hydraulics
boiling water reactors

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

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

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

Review of multi-physics temporal coupling methods for analysis of nuclear reactors

Zerkak, O., Kozlowski, T. & Gajev, I., Jul 28 2015, In : Annals of Nuclear Energy. 84, p. 225-233 9 p.

Research output: Contribution to journalArticle

Nuclear reactors
Physics
Core analysis
Coolants
Numerical methods

Review of Progress in Coated Fuel Particle Performance Analysis

Baghdasaryan, N. & Kozlowski, T., Jan 1 2019, (Accepted/In press) In : Nuclear Science and Engineering.

Research output: Contribution to journalReview article

Coated fuel particles
High temperature gas reactors
Nuclear reactors
Security systems
Coolants

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

Boiling water reactors
Sensitivity analysis
Economics
Uncertainty analysis
sensitivity analysis
Sensitivity analysis
closure law
hydraulics

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 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

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

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

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