20032020
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Research Output 2003 2020

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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 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

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 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
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

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
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

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

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 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

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
Probability density function
Hydraulics
Boundary conditions
Friction
Inlet flow
Uncertainty
Hydraulics
Nuclear engineering
Uncertainty analysis
Void fraction
Statistics
Uncertainty
Nuclear engineering
Light water reactors
Void fraction
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 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 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

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

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
Jacobian matrices
eigenvalue
Eigenvalues and eigenfunctions
eigenvectors
eigenvalues

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

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 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

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

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

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