20032020
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Research Output 2003 2020

2010

Sensitivity and uncertainty of the neutronic parameters of BWR ringhals-1 TRACE/PARCS stability prediction

Gajev, I., Kozlowski, T., Xu, Y. & Downar, T., Dec 1 2010, International Conference on the Physics of Reactors 2010, PHYSOR 2010. p. 3320-3331 12 p. (International Conference on the Physics of Reactors 2010, PHYSOR 2010; vol. 4).

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

boiling water reactors
Boiling water reactors
sensitivity
predictions
hydraulics
2008

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 proceedingConference contribution

Pressure vessels
Reactor shutdowns
Reactor cores
Water levels
Cooling systems

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 proceedingConference contribution

control rods
Control rods
retarding
reactors
hydraulics

Qualification of the 3D Thermal Hydraulics Model of the Code System TRACE Based on plant data

Sánchez, V. H., Jäger, W. & Kozlowski, T., Sep 26 2008, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". p. 1084-1092 9 p. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; vol. 2).

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

Hydraulic models
Pressure vessels
Coolants
Steam piping systems
Nuclear power plants

Relating system-to-CFD coupled code analyses to theoretical framework of a multiscale method

Cadinu, F., 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. 2959-2967 9 p. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; vol. 5).

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

Computational fluid dynamics
Accidents
Fluids
Fluid dynamics
Two phase flow

Simulation of two-phase flow instability in CIRCUS facility using RELAP5

Phung, V. A., Kozlowski, T., Kudinov, P. & Rohde, M., Dec 1 2008, In : Transactions of the American Nuclear Society. 99, p. 813-814 2 p.

Research output: Contribution to journalConference article

Two phase flow

Spatial coupling for BWR stability analysis

Kozlowski, T., Peltonen, J. & Dinh, T. N., Nov 7 2008, In : Transactions of the American Nuclear Society. 98, p. 603-605 3 p.

Research output: Contribution to journalConference article

Spatial coupling for coupled code safety analysis of BWR design-basis accidents

Peltonen, J., Kozlowski, T. & Dinh, T. N., Dec 1 2008, International Conference on the Physics of Reactors 2008, PHYSOR 08. p. 1313-1320 8 p. (International Conference on the Physics of Reactors 2008, PHYSOR 08; vol. 2).

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

Codes (standards)
accidents
hydraulics
safety
Accidents
2007

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 proceedingConference contribution

evaluation
predictions
hydraulics
Hydraulics
two phase flow

RELAP5 and TRACE codes comparison and validation under steady-state and transient conditions on the basis of NUPEC data

Suchoszek, J., Cadinu, F., Kozlowski, T. & 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 proceedingConference contribution

Void fraction
Pressure drop
Boundary conditions
pressure drop
bundles
2006

Multi-physics coupled code reactor analysis with the U.S. NRC code system TRACE/PARCS

Xu, Y., Downar, T., Ward, A., Kozlowski, T. & Ivanov, K., Dec 1 2006, PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics. (PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics; vol. 2006).

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

Physics

RELAP5 performance in predicting critical power in a BWR fuel bundle

Cadinu, F., Kozlowski, T. & Dinh, T. N., Dec 21 2006, In : Transactions of the American Nuclear Society. 95, p. 650-651 2 p.

Research output: Contribution to journalConference article

2005

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 journalConference article

Physics analysis of coolant voiding in the ACR-700 lattice

Cotton, C. A., Lee, D., Kozlowski, T., Downar, T. J., Yang, W. S. & Carlson, D. E., Dec 1 2005, In : Transactions of the American Nuclear Society. 92, p. 685-687 3 p.

Research output: Contribution to journalConference article

Coolants
Physics
2004

Application of SP3 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 journalConference article

Transient analysis

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
Computational Science
Engineering
Students
Computing
Integrate

The use of an Artificial Neural Network for on-line prediction of Pin-Cell Discontinuity Factors in PARCS

Kozlowski, T., Lee, D. & Downar, T. J., Dec 1 2004, Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. p. 613-623 11 p. (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

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

Reactor cores
Simulators
Neural networks
2003

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 journalConference article

Neural networks

OECD/NEA and U.S. NRC PWR MOX/UO 2 core transient benchmark

Kozlowski, T., Cotton, C. A., Downar, T. J. & Lee, R., Dec 1 2003, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 368-371 4 p. (Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy).

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

Kinetics
Plutonium
Transient analysis
Power plants

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