Research Output per year

## Research Output 2003 2020

- 1 - 50 out of 117 results
- Title (ascending)

## 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 journal › Conference article

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 journal › Article

## 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 journal › Conference article

## 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 journal › Article

## 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 journal › Conference article

## 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 journal › Article

## 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 journal › Conference 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 proceeding › Conference contribution

## 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 conference › Paper

## 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 journal › Article

## 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 journal › Article

## 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 journal › Article

## 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 journal › Conference article

## 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 journal › Article

## Application of discrete adjoint method to sensitivity and uncertainty analysis in steady-state two-phase flow simulations

Hu, G. & Kozlowski, T., Apr 2019, In : Annals of Nuclear Energy. 126, p. 122-132 11 p.Research output: Contribution to journal › Article

## 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 journal › Article

## Application of SP_{3} 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 journal › Conference article

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

Hu, G. & Kozlowski, T., Jan 2018, In : Nuclear Engineering and Design. 326, p. 354-370 17 p.Research output: Contribution to journal › Article

## 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 journal › Article

## Assessment of two-phase critical models performance in RELAP5 and TRACE against Marviken critical flow test

Sokolowski, L. & Kozlowski, T., 2010, In : Transactions of the American Nuclear Society. 102, p. 655-657 3 p.Research output: Contribution to journal › Article

## 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 proceeding › Conference contribution

## 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 journal › Conference article

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 journal › Article

## 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 proceeding › Conference contribution

## Comparative neutronics analysis of DIMPLE S06 criticality benchmark with contemporary reactor core analysis computer code systems

Kim, W., Park, J., Kozlowski, T., Lee, H. C. & Lee, D., Jan 1 2015, In : Science and Technology of Nuclear Installations. 2015, 180979.Research output: Contribution to journal › Article

## 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 journal › Article

## 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 journal › Article

## 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 journal › Article

## 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 journal › Article

## Coupling of system thermal-hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error

Wu, X. & Kozlowski, T., Jan 2015, In : Annals of Nuclear Energy. 75, p. 377-387 11 p.Research output: Contribution to journal › Article

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 journal › Article

## 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 journal › Article

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 conference › Paper

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 journal › Review article

## 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 journal › Article

## 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 proceeding › Conference contribution

## Estimation of probability Density Functions for model input parameters using inverse uncertainty quantification with bias terms

Abu Saleem, R. A. & Kozlowski, T., Nov 2019, In : Annals of Nuclear Energy. 133, p. 1-8 8 p.Research output: Contribution to journal › Article

## 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 proceeding › Conference contribution

## 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 proceeding › Conference contribution

## Gaussian Process–Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark

Wang, C., Wu, X. & Kozlowski, T., Jan 1 2018, (Accepted/In press) In : Nuclear Science and Engineering.Research output: Contribution to journal › Article