Research Output per year

## Research Output 2003 2020

- 50 - 100 out of 121 results
- Publication Year, Title (ascending)

## 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 proceeding › Conference contribution

## 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 journal › Article

## 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 proceeding › Conference contribution

## 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 proceeding › Conference contribution

## 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 proceeding › Conference contribution

## 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 proceeding › Conference contribution

## 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

## Inverse uncertainty quantification of input model parameters for thermal-hydraulics simulations using expectation–maximization under Bayesian framework

Shrestha, R. & Kozlowski, T., Apr 25 2016, In : Journal of Applied Statistics. 43, 6, p. 1011-1026 16 p.Research output: Contribution to journal › Article

## 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 journal › Article

## 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 conference › Paper

## On the approximate riemann solver for the two-phase two-fluid six equation model and application to real system

Hu, G. & Kozlowski, T., Jan 1 2016.Research output: Contribution to conference › Paper

## Sensitivity and uncertainty analysis of TRACE Physical Model Parameters based on PSBT benchmark using Gaussian process emulator

Wang, C., Wu, X. & Kozlowski, T., Jan 1 2016.Research output: Contribution to conference › Paper

## Surrogate-based inverse uncertainty quantification of TRACE physical model parameters using steady-state PSBT void fraction data

Wang, C., Wu, X. & Kozlowski, T., Jan 1 2016.Research output: Contribution to conference › Paper

## 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 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

## Inverse uncertainty quantification of reactor simulations under the Bayesian framework using surrogate models constructed by polynomial chaos expansion

Wu, X. & Kozlowski, T., Mar 1 2017, In : Nuclear Engineering and Design. 313, p. 29-52 24 p.Research output: Contribution to journal › Article

## 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 journal › Article

## 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 journal › Conference article

## 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 journal › Conference article

## 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 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

## 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

## 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 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

## 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

## 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

## 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

## 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

## 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

## 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

## 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 proceeding › Conference contribution

## 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 journal › Conference article

## Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark with investigation of measurement bias

Borowiec, K. & Kozlowski, T., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 437-440 4 p.Research output: Contribution to journal › Conference article

## 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 proceeding › Conference contribution

## 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 journal › Article

## Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian Process, Part 2: Application to TRACE

Wu, X., Kozlowski, T., Meidani, H. & Shirvan, K., Aug 15 2018, In : Nuclear Engineering and Design. 335, p. 417-431 15 p.Research output: Contribution to journal › Article

## 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 journal › Article

## Kriging-based inverse uncertainty quantification of nuclear fuel performance code BISON fission gas release model using time series measurement data

Wu, X., Kozlowski, T. & Meidani, H., Jan 2018, In : Reliability Engineering and System Safety. 169, p. 422-436 15 p.Research output: Contribution to journal › Article

## 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 journal › Conference article

## 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 proceeding › Conference contribution

## 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 journal › Conference 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 journal › Conference article

## 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 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

## 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

## 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

## 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