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

Research Output 2003 2020

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

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

Advanced BWR criticality safety part I: Model development, model benchmarking, and depletion with uncertainty analysis

Radaideh, M. I., Price, D., O'Grady, D. & Kozlowski, T., May 2019, In : Progress in Nuclear Energy. 113, p. 230-246 17 p.

Research output: Contribution to journalArticle

Control rods
Uncertainty analysis
benchmarking
uncertainty analysis
Benchmarking

Advanced BWR criticality safety part II: Cask criticality, burnup credit, sensitivity, and uncertainty analyses

Price, D., Radaideh, M. I., O'Grady, D. & Kozlowski, T., Aug 2019, In : Progress in Nuclear Energy. 115, p. 126-139 14 p.

Research output: Contribution to journalArticle

Spent fuels
safety
Isotopes
actinide
Actinides

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 a small PWR core with the PARCS/Helios and PARCS/Serpent code systems

Baiocco, G., Petruzzi, A., Bznuni, S. & Kozlowski, T., Sep 1 2017, In : Annals of Nuclear Energy. 107, p. 42-48 7 p.

Research output: Contribution to journalArticle

Reactor cores
Pressurized water reactors
Physics

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 Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone

Dokhane, A., Judd, J., Gajev, I., Zerkak, O., Ferroukhi, H. & Kozlowski, T., Apr 1 2017, In : Annals of Nuclear Energy. 102, p. 190-199 10 p.

Research output: Contribution to journalArticle

Light water reactors
Hydraulics
Hot Temperature

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

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

Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure

Borowiec, K., Pigg, C. & Kozlowski, T., Jan 1 2019, p. 5239-5252. 14 p.

Research output: Contribution to conferencePaper

sensitivity
Void fraction
simulation
Engines
Fourier analysis

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

A new framework for sampling-based uncertainty quantification of the six-group reactor kinetic parameters

Radaideh, M. I., Wieselquist, W. A. & Kozlowski, T., May 2019, In : Annals of Nuclear Energy. 127, p. 1-11 11 p.

Research output: Contribution to journalArticle

Kinetic parameters
Neutrons
Sampling
Isotopes
Uncertainty

A possible application of catastrophe theory to boiling water reactor instability

Pázsit, I., Dykin, V., Konno, H. & Kozlowski, T., Jan 2020, In : Progress in Nuclear Energy. 118, 103054.

Research output: Contribution to journalArticle

catastrophe theory
Boiling water reactors
hysteresis
Hysteresis
bifurcation

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 continuous adjoint method to steady-state two-phase flow simulations

Hu, G. & Kozlowski, T., Jul 2018, In : Annals of Nuclear Energy. 117, p. 202-212 11 p.

Research output: Contribution to journalArticle

Flow simulation
Two phase flow
Sensitivity analysis
Uncertainty analysis
Boiling liquids
Uncertainty analysis
Flow simulation
Two phase flow
Sensitivity analysis
Boiling water reactors

Application of implicit Roe-type scheme and Jacobian-Free Newton-Krylov method to two-phase flow problems

Hu, G. & Kozlowski, T., Sep 2018, In : Annals of Nuclear Energy. 119, p. 180-190 11 p.

Research output: Contribution to journalArticle

Newton-Raphson method
Eigenvalues and eigenfunctions
Two phase flow
Fluxes
Jacobian matrices

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
Jacobian matrices
Equations of state
equation of state
equations of state
matrix

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

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, In : Transactions of the American Nuclear Society. 118, p. 419-422 4 p.

Research output: Contribution to journalConference article

Calibration
Uncertainty

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

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

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

Radaideh, M. I. & Kozlowski, T., Nov 1 2019, In : International Journal of Energy Research. 43, 14, p. 7866-7890 25 p.

Research output: Contribution to journalArticle

Learning systems
Nuclear engineering
Analysis of variance (ANOVA)
Nuclear energy
Artificial intelligence

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

Confirmation of Wilks’ method applied to TRACE model of boiling water reactor spray cooling experiment

Mui, T. & Kozlowski, T., Jul 2018, In : Annals of Nuclear Energy. 117, p. 53-59 7 p.

Research output: Contribution to journalArticle

Boiling water reactors
Cooling
Experiments
Hydraulics
Statistics

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

reactor cores
Reactor cores
simulators
Simulators
Kinetics

Coupling Methods for HTR-PM Multicircuit Problem

Lu, J., Guo, J., Kozlowski, T. & Li, F., Feb 1 2019, In : Nuclear Science and Engineering. 193, 1-2, p. 131-146 16 p.

Research output: Contribution to journalArticle

Networks (circuits)
Steam generators
Reactor cores
Convergence of numerical methods
Newton-Raphson method

Coupling methods for HTR-PM primary circuit

Lu, J., Guo, J., Kozlowski, T. & Li, F., Jun 2018, In : Annals of Nuclear Energy. 116, p. 20-30 11 p.

Research output: Contribution to journalArticle

High temperature gas reactors
Reactor cores
Networks (circuits)
Newton-Raphson method
Steam generators
Hydraulics
Physics
Uncertainty
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

Criticality and uncertainty assessment of assembly misloading in BWR transportation cask

Radaideh, M. I., Price, D. & Kozlowski, T., Mar 2018, In : Annals of Nuclear Energy. 113, p. 1-14 14 p.

Research output: Contribution to journalArticle

Fission products
Gadolinium
Actinides
Spent fuels
Uncertainty

Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark

Radaideh, M. I., Kozlowski, T., Wieselquist, W. A. & Jessee, M. A., Jan 1 2019, In : Science and Technology of Nuclear Installations. 2019, 3702014.

Research output: Contribution to journalArticle

Open Access
Kinetic parameters
Neutrons
Uncertainty
Control rods
Void fraction

Demonstration of the relationship between sensitivity and identifiability for inverse uncertainty quantification

Wu, X., Shirvan, K. & Kozlowski, T., Nov 1 2019, In : Journal of Computational Physics. 396, p. 12-30 19 p.

Research output: Contribution to journalArticle

Uncertainty Quantification
Identifiability
Calibration
Demonstrations
Discrepancy

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

Determination and validation of photon energy absorption buildup factor in human tissues using Monte Carlo simulation

Jarrah, I., Radaideh, M. I., Kozlowski, T. & Rizwan-uddin, Jul 2019, In : Radiation Physics and Chemistry. 160, p. 15-25 11 p.

Research output: Contribution to journalArticle

energy absorption
photons
simulation
progressions
penetration

Development and assessment of adjoint sensitivity analysis method for transient two-phase flow simulations

Hu, G. & Kozlowski, T., Jan 1 2019, p. 2246-2259. 14 p.

Research output: Contribution to conferencePaper

Flow simulation
sensitivity analysis
two phase flow
Control theory
Two phase flow

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

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

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

Effect of mesh refinement on the estimation of model input parameters using Inverse Uncertainty Quantification

Abu Saleem, R. A. & Kozlowski, T., Oct 2019, In : Annals of Nuclear Energy. 132, p. 271-276 6 p.

Research output: Contribution to journalArticle

Maximum likelihood estimation
Hydraulics
Friction
Sensitivity analysis
Uncertainty

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
Probability density function
Hydraulics
Boundary conditions
Friction
Inlet flow

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
Uncertainty
Hydraulics
Nuclear engineering
Uncertainty analysis
Void fraction