| Benchmark for uncertainty analysis in modeling (UAM) for design, operation and safety analysis of LWRs K Ivanov, M Avramova, S Kamerow, IA Kodeli, E Sartori, E Ivanov, ... OECD Nuclear Energy Agency, 2013 | 327* | 2013 |
| CTF theory manual R Salko Jr, M Avramova, A Wysocki, A Toptan, J Hu, N Porter, T Blyth, ... (No Title), 2020 | 230 | 2020 |
| Oecd/nrc benchmark based on nupec pwr sub-channel and bundle test (psbt). volume i: Experimental database and final problem specifications A Rubin, A Schoedel, M Avramova, H Utsuno, S Bajorek, ... Organisation for Economic Co-Operation and Development, 2012 | 181 | 2012 |
| Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis K Ivanov, M Avramova Annals of Nuclear Energy 34 (6), 501-513, 2007 | 140 | 2007 |
| Verification, validation and uncertainty quantification in multi-physics modeling for nuclear reactor design and safety analysis MN Avramova, KN Ivanov Progress in Nuclear Energy 52 (7), 601-614, 2010 | 99 | 2010 |
| OECD/NEA benchmark for uncertainty analysis in modeling (UAM) for LWRs–summary and discussion of neutronics cases (phase I) RN Bratton, M Avramova, K Ivanov Nuclear Engineering and Technology 46 (3), 313-342, 2014 | 64 | 2014 |
| Development and assessment of a nearly autonomous management and control system for advanced reactors L Lin, P Athe, P Rouxelin, M Avramova, A Gupta, R Youngblood, J Lane, ... Annals of Nuclear Energy 150, 107861, 2021 | 59 | 2021 |
| Development of an innovative spacer grid model utilizing computational fluid dynamics within a subchannel analysis tool M Avramova The Pennsylvania State University, 2007 | 59 | 2007 |
| Development, verification and application of a new model for active nucleation site density in boiling systems Q Li, Y Jiao, M Avramova, P Chen, J Yu, J Chen, J Hou Nuclear Engineering and Design 328, 1-9, 2018 | 53 | 2018 |
| CTF: A thermal hydraulic sub-channel code for LWR transient analyses, user’s manual MN Avramova Pennsylvania State University, Department of Nuclear Engineering, 2009 | 48 | 2009 |
| COBRA-TF Subchannel Thermal-Hydraulics Code (CTF) Theory Manual–Revision 0 RK Salko, MN Avramova The Pennsylvania State University, 2015 | 44 | 2015 |
| Optimization and parallelization of the thermal–hydraulic subchannel code CTF for high-fidelity multi-physics applications RK Salko, RC Schmidt, MN Avramova Annals of Nuclear Energy 84, 122-130, 2015 | 43 | 2015 |
| CTF theory manual MN Avramova, RK Salko Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2016 | 40 | 2016 |
| CFD prediction of critical heat flux in vertical heated tubes with uniform and non-uniform heat flux Q Li, M Avramova, Y Jiao, P Chen, J Yu, Z Pu, J Chen Nuclear Engineering and Design 326, 403-412, 2018 | 38 | 2018 |
| Coupled MCNP6/CTF code: Development, testing, and application A Bennett, M Avramova, K Ivanov Annals of Nuclear Energy 96, 1-11, 2016 | 33 | 2016 |
| New developments of the MCNP/CTF/NEM/NJOY code system–Monte Carlo based coupled code for high accuracy modeling FP Espel, MN Avramova, KN Ivanov, S Misu Annals of Nuclear Energy 51, 18-26, 2013 | 33 | 2013 |
| CTF: A thermal hydraulic sub-channel code for LWR transient analyses MN Avramova, RK Salko User’s Manual, Pennsylvania State University, 2009 | 32 | 2009 |
| Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses M Avramova, D Cuervo, K Ivanov Proceedings: PHYSOR-2006, Vancouver, Canada, 2006 | 32 | 2006 |
| Development of COBRA-TF for modeling full-core, reactor operating cycles R Salko, T Lange, V Kucukboyaci, Y Sung, S Palmtag, J Gehin, ... Advances in Nuclear Fuel Management V (ANFM 2015), 2015 | 31 | 2015 |
| COBRA-TF Subchannel Thermal-Hydraulics Code (CTF) Theory Manual RK Salko, MN Avramova Pennsylvania State University, CASL-U-2015-0054-000, State College, 2015 | 29 | 2015 |
Annalisa ManeraProfessor, Nuclear Engineering and Radiological Sciences, University of MichiganVerified email at umich.edu
