| Year |
Citation |
Score |
| 2020 |
Waite BM, Prasser H, Podowski MZ. Computational and experimental analysis of gas/liquid two-phase flow in rod bundles with mixing-vane spacer grids Nuclear Engineering and Design. 360: 110499. DOI: 10.1016/J.Nucengdes.2019.110499 |
0.519 |
|
| 2019 |
Podowski MZ. Understanding two-phase flow and boiling heat transfer: Challenges and paradoxes Nuclear Engineering and Design. 354: 110185. DOI: 10.1016/J.Nucengdes.2019.110185 |
0.488 |
|
| 2019 |
Podowski MZ. Is reactor multiphase thermal-hydraulics a mature field of engineering science? Nuclear Engineering and Design. 345: 196-208. DOI: 10.1016/J.Nucengdes.2019.01.022 |
0.42 |
|
| 2019 |
Wang Z, Podowski MZ. Analytical modeling of the effect of heater geometry on boiling heat transfer Nuclear Engineering and Design. 344: 122-130. DOI: 10.1016/J.Nucengdes.2018.12.020 |
0.525 |
|
| 2019 |
Podowski MZ, Podowski RM, Kim DH, Bae JH, Son DG. COMPASS - New modeling and simulation approach to PWR in-vessel accident progression Nuclear Engineering and Technology. 51: 1916-1938. DOI: 10.1016/J.Net.2019.06.008 |
0.435 |
|
| 2019 |
Jiao H, Podowski MZ. Formulation and validation of a three-dimensional computational model of simultaneous interfacial evaporation and condensation in subcooled boiling International Journal of Multiphase Flow. 112: 130-154. DOI: 10.1016/J.Ijmultiphaseflow.2018.12.001 |
0.554 |
|
| 2017 |
Bae JH, Son DG, Kim J, Park RJ, Park JH, Kim DH, Song JH, Podowski MZ. Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code Nuclear Engineering and Design. 320: 258-268. DOI: 10.1016/J.Nucengdes.2017.05.030 |
0.344 |
|
| 2016 |
Behafarid F, Podowski MZ. Modeling and computer simulation of centrifugal co2 compressors at supercritical pressures Journal of Fluids Engineering, Transactions of the Asme. 138. DOI: 10.1115/1.4032570 |
0.751 |
|
| 2015 |
Behafarid F, Jansen KE, Podowski MZ. A study on large bubble motion and liquid film in vertical pipes and inclined narrow channels International Journal of Multiphase Flow. 75: 288-299. DOI: 10.1016/J.Ijmultiphaseflow.2015.04.016 |
0.76 |
|
| 2015 |
Waite BM, Shaver DR, Podowski MZ. Mechanistic modeling of two-phase flow around spacer grids with mixing vanes International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 9: 7101-7114. |
0.843 |
|
| 2015 |
Shaver DR, Podowski MZ. Modeling and validation of forced convection subcooled boiling International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 5: 4112-4125. |
0.845 |
|
| 2014 |
Waite BM, Shaver DR, Podowski MZ. Multidimensional mechanistic modeling of fluid flow and heat around spacer grids International Congress On Advances in Nuclear Power Plants, Icapp 2014. 1: 124-133. |
0.843 |
|
| 2014 |
Shaver DR, Podowski MZ. Multidimensional modeling of force convection subcooled boiling in pressurized water reactors Transactions of the American Nuclear Society. 111: 1555-1558. |
0.788 |
|
| 2014 |
Behafarid F, Podowski MZ. A study on numerical modeling of supercritical CO2 flow in centrifugal compressors Embedded Topical Meeting On Advances in Thermal Hydraulics, Ath 2014, Held At the American Nuclear Society 2014 Annual Meeting. 532-544. |
0.734 |
|
| 2013 |
Behafarid F, Shaver D, Bolotnov IA, Antal SP, Jansen KE, Podowski MZ. Coupled dns/rans simulation of fission gas discharge during loss-of-flow accident in generation IV sodium fast reactor Nuclear Technology. 181: 44-55. DOI: 10.13182/Nt13-A15755 |
0.759 |
|
| 2013 |
Waite BM, Shaver DR, Podowski MZ. Prediction of pressure drop and heat transfer around flow obstructions Transactions of the American Nuclear Society. 109: 1624-1627. |
0.808 |
|
| 2013 |
Shaver DR, Podowski MZ. A fundamental model for predicting bubble size in diabatic multiphase flows Transactions of the American Nuclear Society. 109: 1833-1836. |
0.802 |
|
| 2013 |
Behafarid F, Podowski MZ. Multidimensional modeling and simulation of supercritical CO2 compressor Transactions of the American Nuclear Society. 109: 1628-1632. |
0.674 |
|
| 2012 |
Podowski MZ. Toward mechanistic modeling of boiling heat transfer Nuclear Engineering and Technology. 44: 889-896. DOI: 10.5516/Net.02.2012.720 |
0.535 |
|
| 2012 |
Bolotnov IA, Antal SP, Jansen KE, Podowski MZ. Multidimensional analysis of fission gas transport following fuel element failure in sodium fast reactor Nuclear Engineering and Design. 247: 136-146. DOI: 10.1016/J.Nucengdes.2012.02.004 |
0.525 |
|
| 2012 |
Podowski MZ. Mechanistic modeling of boiling heat transfer Advances in Thermal Hydraulics 2012, Ath 2012. 1-5. |
0.446 |
|
| 2012 |
Jiao H, Podowski MZ. An analysis of multidimensional models of gas/liquid flows Transactions of the American Nuclear Society. 107: 1393-1394. |
0.338 |
|
| 2012 |
Bolotnov IA, Podowski MZ. Informing the development of the turbulence models for bubbly gas/liquid flows using interface tracking simulations Advances in Thermal Hydraulics 2012, Ath 2012. 29-37. |
0.433 |
|
| 2012 |
Waite BM, Shaver DR, Podowski MZ. CFD analysis of flow through expansions and contractions in pipes Transactions of the American Nuclear Society. 107: 1336-1338. |
0.791 |
|
| 2012 |
Shaver DR, Antal SP, Podowski MZ. Development, testing and validation of multidimensional model of subcooled boiling Transactions of the American Nuclear Society. 107: 1366-1368. |
0.774 |
|
| 2012 |
Smith WC, Podowski MZ. Theoretical and computational analysis of flow oscillations in S-CO2 natural circulation loop International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 1982-1987. |
0.375 |
|
| 2012 |
Gallaway T, Antal SP, Podowski MZ. On the multidimensional modeling of fluid flow and heat transfer in SCWRS International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 1: 231-239. |
0.816 |
|
| 2012 |
Shaver DR, Antal SP, Podowski MZ. Multidimensional mechanistic modeling of interfacial heat and mass transfer International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 2062-2072. |
0.837 |
|
| 2012 |
Behafarid F, Shaver DR, Bolotnov IA, Jansen KE, Antal SP, Podowski MZ. Multi-scale approach to the modeling of fission gas discharge during hypothetical loss-of-flow accident in gen-IV sodium fast reactor International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 2051-2061. |
0.809 |
|
| 2011 |
Bolotnov IA, Jansen KE, Drew DA, Oberai AA, Lahey RT, Podowski MZ. Detached direct numerical simulations of turbulent two-phase bubbly channel flow International Journal of Multiphase Flow. 37: 647-659. DOI: 10.1016/J.Ijmultiphaseflow.2011.03.002 |
0.466 |
|
| 2011 |
Shaver DR, Bolotnov IA, Antal SP, Podowski MZ. Simulation of fission gas release in a fuel rod bundle of a SFR Transactions of the American Nuclear Society. 105: 1049-1051. |
0.75 |
|
| 2011 |
Bolotnov IA, Podowski MZ. On the modeling of gas/liquid flows using DNS Transactions of the American Nuclear Society. 104: 1089-1090. |
0.33 |
|
| 2011 |
Shaver DR, Antal SP, Podowski MZ. Multidimensional modeling of interfacial boiling and condensation Transactions of the American Nuclear Society. 105: 1040-1041. |
0.797 |
|
| 2010 |
Schlichting WR, Lahey RT, Podowski MZ. An analysis of interacting instability modes, in a phase change system Nuclear Engineering and Design. 240: 3178-3201. DOI: 10.1016/J.Nucengdes.2010.05.057 |
0.713 |
|
| 2010 |
Tselishcheva EA, Antal SP, Podowski MZ. Mechanistic multidimensional analysis of horizontal two-phase flows Nuclear Engineering and Design. 240: 405-415. DOI: 10.1016/J.Nucengdes.2009.09.015 |
0.525 |
|
| 2010 |
Bolotnov IA, Behafarid F, Shaver D, Guo T, Wang S, Wei H, Antal SP, Jansen KE, Samulyak R, Podowski MZ. Interaction of computational tools for multiscale multiphysics simulation of generation-IV reactors International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 3: 1738-1748. |
0.726 |
|
| 2010 |
Gallaway T, Podowski MZ. Stability analysis of fluid at supercritical pressure in a heated channel International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 3: 1592-1598. |
0.801 |
|
| 2010 |
Podowski MZ. A mechanistic approach to the modeling of bubble/bubble interactions in gas/liquid flows Transactions of the American Nuclear Society. 103: 945-947. |
0.319 |
|
| 2009 |
Podowski MZ, Podowski RM. Mechanistic multidimensional modeling of forced convection boiling heat transfer Science and Technology of Nuclear Installations. 2009. DOI: 10.1155/2009/387020 |
0.442 |
|
| 2009 |
Tselishcheva EA, Antal SP, Podowski MZ, Guillen DP, Beyer M, Lucas D. Development and validation of a multifield model of churn-turbulent gas/liquid flows International Conference On Nuclear Engineering, Proceedings, Icone. 5: 317-326. DOI: 10.1115/ICONE17-75210 |
0.416 |
|
| 2009 |
Guillen DP, Shelley JK, Antal SP, Tselishcheva EA, Podowski MZ, Lucas D, Beyer M. Optimization of a two-fluid hydrodynamic model of churn-turbulent flows International Conference On Nuclear Engineering, Proceedings, Icone. 5: 257-266. DOI: 10.1115/ICONE17-75113 |
0.414 |
|
| 2009 |
Podowski MZ. On the consistency of mechanistic multidimensional modeling of gas/liquid two-phase flows Nuclear Engineering and Design. 239: 933-940. DOI: 10.1016/J.Nucengdes.2008.10.022 |
0.524 |
|
| 2009 |
Tiwari P, Antal SP, Podowski MZ. Modeling shear-induced diffusion force in particulate flows Computers and Fluids. 38: 727-737. DOI: 10.1016/J.Compfluid.2008.09.007 |
0.672 |
|
| 2009 |
Gallaway T, Antal SP, Podowski MZ. Mechanistic multidimensional analysis of heat transfer in fluids at supercritical pressures International Congress On Advances in Nuclear Power Plants 2009, Icapp 2009. 3: 1765-1772. |
0.81 |
|
| 2008 |
Podowski MZ. Multidimensional modeling of two-phase flow and heat transfer International Journal of Numerical Methods For Heat and Fluid Flow. 18: 491-513. DOI: 10.1108/09615530810853691 |
0.551 |
|
| 2008 |
Gallaway T, Antal SP, Podowski MZ. Multi-dimensional model of fluid flow and heat transfer in Generation-IV Supercritical Water Reactors Nuclear Engineering and Design. 238: 1909-1916. DOI: 10.1016/J.Nucengdes.2007.11.019 |
0.829 |
|
| 2008 |
Anglart H, Gallaway T, Antal SP, Podowski MZ. Prediction and analysis of onset of turbulent convective heat transfer deterioration in supercritical water flows Societe Francaise D'Energie Nucleaire - International Congress On Advances in Nuclear Power Plants - Icapp 2007, "the Nuclear Renaissance At Work",. 3: 1552-1558. |
0.816 |
|
| 2008 |
Gallaway T, Podowski MZ, Antal SP. Effect of physical properties of fluids at supercritical conditions on local flow and heat transfer in heated channels Societe Francaise D'Energie Nucleaire - International Congress On Advances in Nuclear Power Plants - Icapp 2007, "the Nuclear Renaissance At Work",. 3: 1437-1443. |
0.812 |
|
| 2008 |
Tselishcheva EA, Antal SP, Podowski MZ, Marshall S. Mechanistic multidimensional analysis of two-phase flow in horizontal tube with 90° elbow Societe Francaise D'Energie Nucleaire - International Congress On Advances in Nuclear Power Plants - Icapp 2007, "the Nuclear Renaissance At Work",. 3: 1444-1453. |
0.461 |
|
| 2007 |
Wierzbicki BZ, Antal SP, Podowski MZ. On the modeling of gas bubble evolution and transport using coupled level-set/CFD method Nuclear Technology. 158: 261-274. DOI: 10.13182/Nt07-A3841 |
0.516 |
|
| 2007 |
Gallaway T, Antal SP, Podowski MZ, Bae YY, Cho BH, Wolf JR. The development of a modeling framework for multidimensional analysis of flow and heat transfer in supercritical fluids Proceedings - 12th International Topical Meeting On Nuclear Reactor Thermal Hydraulics, Nureth-12. |
0.81 |
|
| 2007 |
Guillen DP, Wendt DS, Antal SP, Podowski MZ. Review of experimental capabilities and hydrodynamic data for validation of CFD based predictions for slurry bubble column reactors Aiche Annual Meeting, Conference Proceedings. |
0.304 |
|
| 2007 |
Podowski MZ, Green L, Czajkowski J. Thermal-hydraulic analysis of Reheater Drains System during initial emergency cooling water injection conditions in CANDU reactors Proceedings - 12th International Topical Meeting On Nuclear Reactor Thermal Hydraulics, Nureth-12. |
0.367 |
|
| 2007 |
Gallaway T, Antal SP, Podowski MZ, Guillen DP. NPHASE predictions of turbulent flow in the lower plenum of a prismatic gas-cooled reactor Proceedings - 12th International Topical Meeting On Nuclear Reactor Thermal Hydraulics, Nureth-12. |
0.804 |
|
| 2006 |
Vafaei S, Borca-Tasciuc T, Podowski MZ, Purkayastha A, Ramanath G, Ajayan PM. Effect of nanoparticles on sessile droplet contact angle. Nanotechnology. 17: 2523-7. PMID 21727499 DOI: 10.1088/0957-4484/17/10/014 |
0.582 |
|
| 2006 |
Gallaway T, Antal SP, Podowski MZ. Multidimensional model of fluid flow and heat transfer in generation-IV supercritical water reactors International Conference On Nuclear Engineering, Proceedings, Icone. 2006. DOI: 10.1115/ICONE14-89897 |
0.823 |
|
| 2006 |
Aniel-Buchheit S, Podowski MZ. On the modeling of local neutronically-coupled flow-induced oscillations in advanced boiling water reactors International Conference On Nuclear Engineering, Proceedings, Icone. 2006. DOI: 10.1115/ICONE14-89867 |
0.419 |
|
| 2006 |
Tiwari P, Antal SP, Podowski MZ. Three-dimensional fluid mechanics of particulate two-phase flows in U-bend and helical conduits Physics of Fluids. 18. DOI: 10.1063/1.2189212 |
0.662 |
|
| 2006 |
Podowski MZ, Antal SP, Anglart H. Development of mechanistic modeling capabilities for generation-IV supercritical water-cooled reactor (SCWR) Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 392-397. |
0.741 |
|
| 2005 |
Vafaei S, Podowski MZ. Analysis of the relationship between liquid droplet size and contact angle. Advances in Colloid and Interface Science. 113: 133-46. PMID 15904888 DOI: 10.1016/J.Cis.2005.03.001 |
0.632 |
|
| 2005 |
Vafaei S, Podowski MZ. Theoretical analysis on the effect of liquid droplet geometry on contact angle Nuclear Engineering and Design. 235: 1293-1301. DOI: 10.1016/J.Nucengdes.2005.02.026 |
0.62 |
|
| 2005 |
Podowski MZ. Understanding multiphase flow and heat transfer: Perception, reality, future needs Archives of Thermodynamics. 26: 3-20. |
0.438 |
|
| 2004 |
Tiwari P, Antal SP, Burgoyne A, Belfort G, Podowski MZ. Multifield computational fluid dynamics model of particulate flow in curved circular tubes Theoretical and Computational Fluid Dynamics. 18: 205-220. DOI: 10.1007/S00162-004-0127-3 |
0.628 |
|
| 2004 |
Tiwari P, Antal SP, Podowski MZ. Computational study of particle/liquid flows in curved/coiled membrane systems Aiche Annual Meeting, Conference Proceedings. 5217-5228. |
0.352 |
|
| 2003 |
Tiwari P, Antal SP, Podowski MZ. On the modeling of dispersed particulate flows using a multified model Computational Fluid and Solid Mechanics 2003. 1160-1165. DOI: 10.1016/B978-008044046-0.50284-0 |
0.401 |
|
| 2002 |
Anglart H, Podowski MZ. Fluid mechanics of Taylor bubbles and slug flows in vertical channels Nuclear Science and Engineering. 140: 165-171. DOI: 10.13182/Nse02-A2252 |
0.708 |
|
| 2001 |
Zhou J, Podowski MZ. Modeling and analysis of hydrodynamic instabilities in two-phase flow using two-fluid model Nuclear Engineering and Design. 204: 129-142. DOI: 10.1016/S0029-5493(00)00364-2 |
0.457 |
|
| 1997 |
Kim SW, Podowski MZ, Lahey RT, Kurul N. The modeling of core melting and in-vessel corium relocation in the APRIL code Nuclear Engineering and Design. 177: 265-283. DOI: 10.1016/S0029-5493(97)00199-4 |
0.431 |
|
| 1997 |
Anglart H, Nylund O, Kurul N, Podowski MZ. CFD prediction of flow and phase distribution in fuel assemblies with spacers Nuclear Engineering and Design. 177: 215-228. DOI: 10.1016/S0029-5493(97)00195-7 |
0.731 |
|
| 1997 |
Podowski MZ, Rosa MP. Modeling and numerical simulation of oscillatory two-phase flows, with application to boiling water nuclear reactors Nuclear Engineering and Design. 177: 179-188. DOI: 10.1016/S0029-5493(97)00139-8 |
0.471 |
|
| 1995 |
Taleyarkhan RP, Podowski MZ. An Analysis of Molten-Corium-Induced Failure of Drain Pipes in BWR Mark II Containments Chemical Engineering Communications. 134: 51-72. DOI: 10.1080/00986449508936322 |
0.335 |
|
| 1994 |
Pinheiro Rosa M, Podowski MZ. Nonlinear effects in two-phase flow dynamics Nuclear Engineering and Design. 146: 277-288. DOI: 10.1016/0029-5493(94)90335-2 |
0.504 |
|
| 1994 |
Taleyarkhan RP, McFarlane AF, Lahey RT, Podowski MZ. Benchmarking and qualification of the nufreq-npw code for best estimate prediction of multichannel core stability margins Nuclear Engineering and Design. 151: 157-171. DOI: 10.1016/0029-5493(94)90040-X |
0.402 |
|
| 1991 |
Kim SW, Podowski MZ, Lahey RT, Kim SH. Model of BWR containment thermal-hydraulics under severe accident conditions American Society of Mechanical Engineers, Heat Transfer Division, (Publication) Htd. 165: 83-91. |
0.317 |
|
| 1989 |
Lahey RT, Podowski MZ. On The Analysis Of Various Instabilities In Two-Phase Flows Multiphase Science and Technology. 4: 183-370. DOI: 10.1615/Multscientechn.V4.I1-4.30 |
0.392 |
|
| 1987 |
Taleyarkhan R, Podowski MZ, Lahey RT. The effect of fuel rod dynamics on BWR stability margin Nuclear Engineering and Design. 99: 5-13. DOI: 10.1016/0029-5493(87)90102-6 |
0.365 |
|
| 1987 |
Koh BR, Podowski MZ, Lahey RT. MODELING OF BWR THERMAL-HYDRAULICS FOR SEVERE ACCIDENTS ANALYSIS Aiche Symposium Series. 83: 320-325. |
0.417 |
|
| 1987 |
Kim DH, Podowski MZ, Lahey RT. MODELING OF REACTOR PRESSURE VESSEL FAILURE MODES DURING CORE MELTDOWN ACCIDENTS OF BWRs American Society of Mechanical Engineers (Paper). |
0.387 |
|
| 1986 |
Park GC, Podowski MZ, Becker M, Lahey RT, Peng SJ. The development of a closed-form analytical model for the stability analysis of nuclear-coupled density-wave oscillations in boiling water nuclear reactors Nuclear Engineering and Design. 92: 253-281. DOI: 10.1016/0029-5493(86)90250-5 |
0.438 |
|
| 1986 |
Taleyarkhan RP, Podowski MZ, Lahey RT. A stability analysis of ventilated boiling channels Nuclear Engineering and Design. 93: 39-50. DOI: 10.1016/0029-5493(86)90193-7 |
0.472 |
|
| 1986 |
Peng SJ, Podowski MZ, Lahey RT. BWR linear stability analysis Nuclear Engineering and Design. 93: 25-37. DOI: 10.1016/0029-5493(86)90192-5 |
0.478 |
|
| 1985 |
Taleyarkhan R, Podowski M, Lahey RT. An Instability Analysis of Ventilated Channels Journal of Heat Transfer-Transactions of the Asme. 107: 175-181. DOI: 10.1115/1.3247375 |
0.326 |
|
| 1984 |
Peng SJ, Podowski MZ, Lahey RT, Becker M. NUFREQ-NP: A COMPUTER CODE FOR THE STABILITY ANALYSIS OF BOILING WATER NUCLEAR REACTORS Nuclear Science and Engineering. 88: 404-411. DOI: 10.13182/Nse84-A18594 |
0.347 |
|
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