20032020
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Research Output 2003 2020

2015

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., Jan 1 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 3768-3778 11 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 5).

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

boiling
Boiling liquids
heat transfer
maximum likelihood estimates
Experiments
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., 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 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
2017

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 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
chaotic dynamics
Chaos theory
chaos
polynomials
reactors

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
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

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

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

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

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

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

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

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
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
Uncertainty

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

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
Nuclear fuels
Time series
Gases
Nuclear reactors
Principal component analysis

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 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

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

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

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
2019

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

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

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