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

Research Output 2003 2020

2017

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

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

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
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

A solver for the two-phase two-fluid model based on high-resolution total variation diminishing scheme

Abu Saleem, R. A., Kozlowski, T. & Shrestha, R., May 1 2016, In : Nuclear Engineering and Design. 301, p. 255-263 9 p.

Research output: Contribution to journalArticle

Ability testing
TVD schemes
two fluid models
Shock tubes
Convergence of numerical methods
Uncertainty Quantification
Expectation Maximization
Hydraulics
Simulation
Model Uncertainty

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

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
Jacobian matrices
Eigenvalues and eigenfunctions
eigenvectors
eigenvalues
Fluids
Uncertainty analysis
sensitivity analysis
Sensitivity analysis
closure law
hydraulics
Void fraction
voids
simulation
Markov chains
estimates
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
Criticality (nuclear fission)
Core analysis
Reactor cores
Physics
Scattering
Hydraulics
Physics
Uncertainty
Hot Temperature

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

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

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

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

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

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

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

Neutrons
Hydraulics
Kinetics
Uncertainty analysis
Hot Temperature

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

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

Boiling water reactors
Neutrons
Hydraulics
Kinetics
Hot Temperature

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

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 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
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

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

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
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

Two phase flow
Physics
Fluids

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

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

Neutrons
Hydraulics
Kinetics
Hot Temperature
Test facilities
Cooling
Experiments
Temperature
Uncertainty

Trace V5 code application dvi line break loca using atlas facility

Veronese, F. & Kozlowski, 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
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

Homogenization method
Neutrons
Fluxes
Reactor cores
Simulators

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

hydraulics
Neutrons
reactivity
Hydraulics
neutrons

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

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
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