Curriculum Vitae

Personal Information

Name:  Gholam Reza Ansarifar (Associate Professor)

Address:  Department of Nuclear Engineering, Faculty of  

                Physics, University of Isfahan, Isfahan 81746-73441, Iran.

Tel:   +98-31-37934784

Fax:   +98-31-37932723

E-mail: ghr.ansarifar@ast.ui.ac.ir

Education

Ph.D., 2012, Nuclear Engineering-Reactor engineering, Amir Kabir University of Technology, Tehran, Iran [Thesis: Dynamic sliding mode control for non-minimum phase systems with minimum measurable states and its application to water level control in  the nuclear steam generators]

M.Sc., 2009, Mechanical Engineering- dynamic&control, Amir Kabir University of Technology, Tehran, Iran.

B.Sc., 2007, Mechanical Engineering- dynamic&control, Amir Kabir University of Technology, Tehran, Iran.

Research Interests

Nuclear reactors modeling, dynamics and control of nuclear reactors and thermal hydraulic systems, Thermal hydraulic analysis of nuclear reactors, control and modeling of energy systems, adaptive robust control design for power systems, nuclear fuel management and fuel technology.

Publications:

Nanofluid applications in pressurized water reactors: A review SF Mirian, GR Ansarifar, MH Esteki International Journal of Energy Research 46 (15), 22314-22335		2022
Experimental analysis of forced convection heat transfer of Hybrid Nanofluids in a vertical annulus with cosine heat flux M Talebi, MA Borhani, SMM Zadeh, GR Ansarifar Progress in Nuclear Energy 153, 104438	2	2022
Conceptual design of a new space nuclear reactor with low‐enriched uranium fuel based on the optimization of fuel composition and reflector geometry via optimized adaptive … M Rafiei, G Ansarifar International Journal of Energy Research 46 (7), 9456-9485		2022
Assessment of gadolinium concentration effects on the NuScale reactor parameters and optimizing the fuel composition via machine learning method A Shahmirzaei, GR Ansarifar, A Koraniany International Journal of Energy Research 46 (7), 8838-8871		2022
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	1	2022
Design of a new Small Modular Nuclear Reactor using TVS-2M Fuel Assemblies and Fuel Depletion analysis during the fresh-core cycle length GR Ansarifar Nuclear Engineering and Design 385, 111540	2	2021
Optimization of the TiO2 nanofluid as a coolant in the VVER-1000 nuclear reactor based on the thermal reactivity feedback coefficients via the genetic algorithm R Kianpour, GR Ansarifar Kerntechnik 86 (6), 419-436		2021
Space nuclear reactor fuel design based on dynamic analysis and GA & PSO optimization M Rafiei, GR Ansarifar Progress in Nuclear Energy, 104043	3	2021
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects M Rafiei, GR Ansarifar, K Hadad, M Mohammadi Progress in Nuclear Energy 141, 103936	4	2021
Pressurizer water level control with estimation of primary circuit coolant mass in nuclear power plants via robust observer based dynamic sliding mode control SM Mostafavi, GR Ansarifar Annals of Nuclear Energy 161, 108413	4	2021
Predicting and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters in the NuScale nuclear reactor using nanofluid as a coolant via machine learning … Z Rahnama, GR Ansarifar Annals of Nuclear Energy 161, 108375	10	2021
Comparative investigation of temperature reactivity feedback coefficients in a pressurized water reactor (PWR) with Alumina (Al2O3) and Titania (TiO2) nano-fluids as coolant R Kianpour, GR Ansarifar Journal of Nuclear Science and Technology (JonSat) 42 (3), 119-128	1	2021
Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic … Z Rahnama, GR Ansarifar Progress in Nuclear Energy 138, 103796	11	2021
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	2	2020
Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using Thermal hydraulic and neutronic analysis … R Kianpour, GR Ansarifar, M Fathi Annals of Nuclear Energy 148, 107682	8	2020
Observer based adaptive robust Feedback-linearization control for VVER-1000 nuclear reactors with bounded axial power distribution based on the validated multipoint kinetics … GR Ansarifar Annals of Nuclear Energy 142, 107380	6	2020
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	8	2020
Optimal design of a Small Modular Reactor core with dual cooled annular fuel based on the neutronics and natural circulation parameters MZ Nejad, GR Ansarifar Nuclear Engineering and Design 360, 110518	11	2020
Design of a Small Modular Nuclear Reactor with dual cooled annular fuel and investigation of the fuel inner radius effect on the power peaking factor and natural circulation … MZ Nejad, GR Ansarifar Annals of Nuclear Energy 138, 107185	9	2020
Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development Z Tabadar, GR Ansarifar, A Pirouzmand Progress in nuclear energy 117, 103101	13	2019
Assessment of the nano-fluid effects on the thermal reactivity feedback coefficients in the VVER-1000 nuclear reactor with nano-fluid as a coolant using thermal hydraulic and … R Kianpour, GR Ansarifar Annals of Nuclear Energy 133, 623-636	11	2019
Stability analysis of linear FNPK model considering reactivity feedback effects for a research nuclear reactor M Rafiei, GR Ansarifar, K Hadad, M Mohammadi Progress in Nuclear Energy 117, 103081	4	2019
Core power control of a nuclear research reactor during power maneuvering transients using optimized PID-controller based on the fractional neutron point kinetics model with … M Rafiei, GR Ansarifar, K Hadad IEEE Transactions on Nuclear Science 66 (7), 1804-1812	7	2019
Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink accident using … Z Tabadar, GR Ansarifar, A Pirouzmand Annals of Nuclear Energy 127, 53-67	15	2019
Reactivity worth calculation for control rods groups of the VVER-1000 nuclear reactor core considering shadowing effect using Monte Carlo method Z Tabadar, GR Ansarifar, K Hadad, M Jabbari International Journal of Nuclear Energy Science and Technology 13 (3), 274-294		2019
Adaptive observer based adaptive control for PWR nuclear reactors during load following operation with bounded xenon oscillations using Lyapunov approach GR Ansarifar Annals of Nuclear Energy 121, 382-405	10	2018
Control of the reactor core power in PWR using optimized PID controller with the real-coded GA SMH Mousakazemi, N Ayoobian, GR Ansarifar Annals of Nuclear Energy 118, 107-121	51	2018
Control of the pressurized water nuclear reactors power using optimized proportional–integral–derivative controller with particle swarm optimization algorithm SMH Mousakazemi, N Ayoobian, GR Ansarifar Nuclear Engineering and Technology 50 (6), 877-885	33	2018
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	13	2018
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation GR Ansarifar Nuclear Engineering and Technology 50 (1), 97-106	10	2018
Numerical simulation of the nuclear reactors kinetics behavior using method of lines based on the GDQ method GR Ansarifar, SM Alavijeh Annals of Nuclear Energy 112, 808-828		2018
Estimation of the poisons reactivity in the PWR Nuclear Reactors using modified higher order sliding mode observer based on the multi-point nuclear reactor model GR Ansarifar Annals of Nuclear Energy 112, 158-169	12	2018
System identification of a research nuclear reactor versus loss of flow accident using recurrent neural network B Salmasian, GR Ansarifar, SM Mirvakili International Journal of Nuclear Energy Science and Technology 12 (3), 283-293	1	2018
Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach M Zaidabadinejad, GR Ansarifar Kerntechnik 82 (5), 586-597		2017
Estimation of axial xenon oscillations with online parameter adaptation in the PWR nuclear reactors using Lyapunov approach based on the multipoint kinetics reactor model GR Ansarifar Annals of Nuclear Energy 108, 277-300	6	2017
Adaptive robust control for axial offset in the PWR nuclear reactors based on the multipoint reactor model during load-following operation GR Ansarifar Annals of Nuclear Energy 103, 251-264	18	2017
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	26	2017
Extended Kalman filter design to estimate the poisons concentrations in the PWR nuclear reactors based on the reactor power measurement MHZ Ygane, GR Ansarifar Annals of Nuclear Energy 101, 576-585	14	2017
Robust observer-based non-linear control for PWR nuclear reactors with bounded xenon oscillations during load-following operation using two-point nuclear reactor model S Saadatzi, G Ansarifar International Journal of Nuclear Energy Science and Technology 11 (1), 22-55	5	2017
Nonlinear observer based control for travelling wave nuclear reactors based on the Lyapunov approach during load following operation R Hassanvand, GR Ansarifar, MN Nasrabadi Journal of Process Control 46, 84-91	11	2016
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	5	2016
Robust nonlinear control for nuclear reactors using sliding mode observer to estimate the xenon concentration GR Ansarifar, HR Akhavan Nuclear Science and Techniques 27, 1-9	3	2016
Investigation of the nano fluid effects on heat transfer characteristics in nuclear reactors with dual cooled annular fuel using CFD (Computational Fluid Dynamics) modeling M Ebrahimian, GR Ansarifar Energy 98, 1-14	25	2016
Control of the nuclear steam generators using adaptive dynamic sliding mode method based on the nonlinear model GR Ansarifar Annals of Nuclear Energy 88, 280-300	26	2016
Non-linear control of the reactor power in a PWR using online parameter adaptation R Ghasemi, GR Ansarifar International Journal of Nuclear Energy Science and Technology 10 (1), 28-58		2016
Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel GR Ansarifar, M Ebrahimian Annals of Nuclear Energy 87, 39-47	21	2016
Core Power Control of the fast nuclear reactors with estimation of the delayed neutron precursor density using Sliding Mode method GR Ansarifar, MN Nasrabadi, R Hassanvand Nuclear Engineering and Design 296, 1-8	15	2016
Numerical simulation of the combined nanofluid effects on heat transfer characteristics in VVER-1000 nuclear reactor SMM Zadeh, GR Ansarifar, M Talebi International Journal of Nuclear Energy Science and Technology 10 (2), 164-182	1	2016
Numerical solution of the neutron diffusion equations as eigenvalue problem in the nuclear reactors using GDQ method GR Ansarifar, SM Alavijeh International Journal of Nuclear Energy Science and Technology 10 (4), 302-312		2016
Nonlinear control for core power of pressurized water nuclear reactors using constant axial offset strategy GR Ansarifar, S Saadatzi Nuclear Engineering and Technology 47 (7), 838-848	27	2015
Assessment of the TiO2/water nanofluid effects on heat transfer characteristics in VVER-1000 nuclear reactor using CFD modeling SM Mousavizadeh, GR Ansarifar, M Talebi Nuclear Engineering and Technology 47 (7), 814-826	36	2015
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	5	2015
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	24	2015
Power calculation of VVER-1000 reactor using a thermal method, applied to primary–secondary circuits M Jabbari, K Hadad, GR Ansarifar, Z Tabadar, M Hashemi-Tilehnoee Annals of Nuclear Energy 77, 129-132	9	2015
Second-order sliding-mode control for a pressurized water nuclear reactor considering the xenon concentration feedback GR Ansarifar, M Rafiei Nuclear Engineering and Technology 47 (1), 94-101	34	2015
Sliding mode control for pressurized-water nuclear reactors in load following operations with bounded xenon oscillations GR Ansarifar, S Saadatzi Annals of Nuclear Energy 76, 209-217	30	2015
Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operation GR Ansarifar, HR Akhavan Annals of Nuclear Energy 75, 611-619	54	2015
Higher order sliding mode controller design for a research nuclear reactor considering the effect of xenon concentration during load following operation GR Ansarifar, M Rafiei Annals of Nuclear Energy 75, 728-735	26	2015
Drift flux modeling of the VVER-1000 horizontal nuclear steam generator V Ghazanfari, GR Ansarifar, MH Esteki Progress in Nuclear Energy 76, 36-43	12	2014
Dynamic Sliding Mode Control of Nuclear Steam Generators Using Out-Put Feedback Based on a Nonlinear Model GR Ansarifar, HA Talebi Journal of Nuclear Science and Technology (JonSat) 34 (3), 46-64		2013
Adaptive estimator-based dynamic sliding mode control for the water level of nuclear steam generators GR Ansarifar, HA Talebi, H Davilu Progress in Nuclear Energy 56, 61-70	32	2012
An adaptive-dynamic sliding mode controller for non-minimum phase systems GR Ansarifar, HA Talebi, H Davilu Communications in Nonlinear Science and Numerical Simulation 17 (1), 414-425	15	2012
Gain scheduled dynamic sliding mode control for nuclear steam generators GR Ansarifar, H Davilu, HA Talebi Progress in nuclear energy 53 (6), 651-663	33	2011
Sliding mode observer and control design with adaptive parameter estimation for a supersonic flight vehicle M Bahrami, B Ebrahimi, GR Ansarifar International Journal of Aerospace Engineering 2010	15	2010
Sliding mode autopilot and observer design for a supersonic flight vehicle M Bahrami, B Ebrahimi, GR Ansarifar, J Roshanian 2008 2nd International Symposium on Systems and Control in Aerospace and …

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Awards and Honors

 Outstanding researcher at Faculty of Advanced Sciences and Technologies- University of Isfahan. (2016)