| Thermal hydraulic analysis of VVER-1000 nuclear reactor with dual-cooled annular fuel using K–ω SST Turbulence model M Zaidabadi, GR Ansarifar, MH Esteki Annals of Nuclear Energy 101, 118-127, 2017 | 37 | 2017 |
| Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model GR Ansarifar, MH Esteki, M Arghand Progress in nuclear energy 79, 104-114, 2015 | 28 | 2015 |
| Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model AF Pilehvar, MH Esteki, A Hedayat, GR Ansarifar Nuclear engineering and technology 50 (5), 654-664, 2018 | 17 | 2018 |
| Evaluation of compressible flow in spherical fueled reactors using the porous media model AF Pilehvar, M Aghaie, MH Esteki, A Zolfaghari, A Minuchehr, A Daryabak, ... Annals of Nuclear Energy 57, 185-194, 2013 | 17 | 2013 |
| Study of perforated plate effect in horizontal WWER1000 steam generator A Safavi, MR Abdi, M Aghaie, MH Esteki, A Zolfaghair, AF Pilevar, ... Nuclear Engineering and design 256, 249-255, 2013 | 14 | 2013 |
| Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor AF Pilehvar, MH Esteki, GR Ansarifar, A Hedayat Annals of Nuclear Energy 139, 107279, 2020 | 12 | 2020 |
| Drift flux modeling of the VVER-1000 horizontal nuclear steam generator V Ghazanfari, GR Ansarifar, MH Esteki Progress in Nuclear Energy 76, 36-43, 2014 | 12 | 2014 |
| Design of the CAREM nuclear reactor core with dual cooled annular fuel and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters S Nasiri, GR Ansarifar, MH Esteki Annals of Nuclear Energy 169, 108939, 2022 | 11 | 2022 |
| Investigation of the dual-cooled annular fuel effect on the thermal power uprate in a VVER-1000 nuclear reactor GR Ansarifar, MH Esteki, M Zaidabadi Nuclear Technology 195 (1), 105-109, 2016 | 10 | 2016 |
| Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3. 2 code M Karimpour, MH Esteki Progress in Nuclear Energy 79, 158-166, 2015 | 8 | 2015 |
| Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors A Safavi, MH Esteki, SM Mirvakili, MK Arani Nuclear Engineering and Technology 52 (8), 1603-1610, 2020 | 7 | 2020 |
| Thermal-hydraulic noise analysis of a VVER-1000 reactor with nanofluid as coolant R Nourollahi, MH Esteki, G Jahanfarnia Progress in Nuclear Energy 108, 334-350, 2018 | 7 | 2018 |
| Estimation of the xenon concentration and delayed neutrons precursors densities in the pressurized-water nuclear reactors (PWR) with sliding mode observer considering xenon … MH Esteki, GR Ansarifar, M Arghand Annals of Nuclear Energy 77, 1-22, 2015 | 6 | 2015 |
| Nanofluid applications in pressurized water reactors: A review SF Mirian, GR Ansarifar, MH Esteki International Journal of Energy Research 46 (15), 22314-22335, 2022 | 4 | 2022 |
| Neutronic analysis of a VVER-1000 reactor with nanofluid as coolant through zeroth order average current nodal expansion method R Nourollahi, MH Esteki, G Jahanfarnia Progress in Nuclear Energy 116, 46-61, 2019 | 4 | 2019 |
| Comparison of back propagation network and radial basis function network in departure from nucleate boiling ratio (DNBR) calculation A Safavi, MH Esteki, SM Mirvakili, M Khaki Kerntechnik 85 (1), 15-25, 2020 | 3 | 2020 |
| Nonlinear stability analysis of a self-pressurized, natural circulation integral reactor via the Lyapunov's second method AF Pilehvar, MH Esteki, GR Ansarifar, A Hedayat Annals of Nuclear Energy 148, 107692, 2020 | 2 | 2020 |
| A coupled thermohydraulic/neutronic investigation of noise propagation in VVER-1000 reactor usingAl2O3 nanofluid coolant R Nourollahi, MH Esteki, G Jahanfarnia Progress in Nuclear Energy 125, 103333, 2020 | 2 | 2020 |
| Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents MK Arani, MH Esteki, N Ayoobian Annals of Nuclear Energy 114, 206-213, 2018 | 2 | 2018 |
| Plasma boundary determination in Damavand tokamak by using current filament method R Ghadiri, Y Sadeghi, MH Esteki International Journal of Modern Physics E 23 (05), 1450033, 2014 | 2 | 2014 |
