20032020
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Research Output 2003 2020

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2020

A possible application of catastrophe theory to boiling water reactor instability

Pázsit, I., Dykin, V., Konno, H. & Kozlowski, T., Jan 1 2020, In : Progress in Nuclear Energy. 118, 103054.

Research output: Contribution to journalArticle

catastrophe theory
Boiling water reactors
hysteresis
Hysteresis
bifurcation
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 1 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 1 2019, In : Progress in Nuclear Energy. 115, p. 126-139 14 p.

Research output: Contribution to journalArticle

Spent fuels
safety
Isotopes
actinide
Actinides

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

Radaideh, M. I., Wieselquist, W. A. & Kozlowski, T., May 1 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

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

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

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 1 2019, In : Radiation Physics and Chemistry. 160, p. 15-25 11 p.

Research output: Contribution to journalArticle

energy absorption
photons
simulation
progressions
penetration

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

Abu Saleem, R. A. & Kozlowski, T., Oct 1 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
Probability density function
Hydraulics
Boundary conditions
Friction
Inlet flow
Statistics
Uncertainty
Nuclear engineering
Light water reactors
Void fraction

Loss of coolant accident analysis under restriction of reverse flow

Radaideh, M. I., Kozlowski, T. & Farawila, Y. M., Jan 1 2019, In : Nuclear Engineering and Technology.

Research output: Contribution to journalArticle

Open Access
Loss of coolant accidents
Coolants
Temperature
Boiling water reactors
Cooling water
Jacobian matrices
eigenvalue
Eigenvalues and eigenfunctions
eigenvectors
eigenvalues

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 1 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
2018

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

Hu, G. & Kozlowski, T., Jul 1 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 1 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

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

Hu, G. & Kozlowski, T., Jan 1 2018, In : Nuclear Engineering and Design. 326, p. 354-370 17 p.

Research output: Contribution to journalArticle

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

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

Mui, T. & Kozlowski, T., Jul 1 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 1 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 1 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

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 1 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
2017

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
2016

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
2015
Criticality (nuclear fission)
Core analysis
Reactor cores
Physics
Scattering
Hydraulics
Physics
Uncertainty
Hot Temperature

Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident

Lee, D., Kozlowski, T. & Downar, T. J., Jan 1 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

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
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

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
2013

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

Kozlowski, T., Peltonen, J., Gajev, I., Phung, V. A. & Roshan, S., 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

Sensitivity and uncertainty of OECD benchmark ringhals-1 TRACE/PARCS stability prediction

Gajev, I., Kozlowski, T., Xu, Y. & Downar, T., Jan 1 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

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., Jan 1 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., Jan 1 2011, In : Nuclear Technology. 176, 2, p. 195-210 16 p.

Research output: Contribution to journalArticle

hydraulics
Neutrons
reactivity
Hydraulics
neutrons