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Electrical Engineering
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Faculty of Engineering
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Electrical Engineering
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Journal Articles
- Loading pattern optimization of the multi-batch boron-free core by the coati optimization algorithm
- KOREAN NUCLEAR SOC
- The effect of different mission proles and ambient temperature on the lifetime of boost converter IGBT with a robust controller in a hybrid electric vehicle
- INST ENGINEERING TECHNOLOGY-IET
- Multi-objective loading pattern optimization of a soluble boron free core using social spider algorithm
- ELSEVIER SCIENCE SA
- Simulation and analysis of core barrel vibrational modes associated with neutron noise phenomena in WWER-type reactors
- ELSEVIER SCIENCE SA
- A comprehensive analysis of thermal-hydraulic signatures in neutron noise of WWER-type reactors
- ELSEVIER SCIENCE SA
- Preventive Framework for Resilience Enhancement in Networked Microgrids: A Focus on Hydrogen Integration and Optimal Energy Management
- INST ENGINEERING TECHNOLOGY-IET
- The large-break LOCA uncertainty analysis in a VVER-1000 reactor using TRACE and DAKOTA
- ELSEVIER SCIENCE SA
- Central hole radius optimization of fuel pellet in WWER-1000 using artificial bee colony and genetic optimization algorithms
- PERGAMON-ELSEVIER SCIENCE LTD
- Uncertainty and sensitivity analysis of generation expansion planning in hybrid nuclear and renewable energy system
- PERGAMON-ELSEVIER SCIENCE LTD
- Modeling and simulation of neutron noise triggered by fuel assembly vibrations in 3D hexagonal geometry
- ELSEVIER SCIENCE SA
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Kerntechnik
- Scientometrics in the Field of Nuclear Science in Iran based on Articles Indexed in the Web of Science
- علم سنجي کاسپين
- Evaluation of advanced accumulator in a VVER-1000 reactor in loss of coolant accident
- Annals of Nuclear Energy
- Designing a molten core collection chamber for Bushehr-1 nuclear power plant using MELCOR 1.8.6 and ANSYS-FLUENT codes
- PERGAMON-ELSEVIER SCIENCE LTD
- Estimation of effective B-fraction of the VVER-1000 reactor in terms of exposure using DRAGON5/DONJON5
- Radiation Physics and Engineering
- Application of metaheuristics optimization in fuel rod design: A case study for helium charging pressure
- Progress in Nuclear Energy
- Full scope simulation of VVER-1000 blowdown source and containment pressurization in a LBLOCA by parallel coupling of TRACE and CONTAIN
- Progress in Nuclear Energy
- A fractional PID controller based on fractional point kinetic model and particle swarm optimization for power regulation of SMART reactor
- Nuclear Engineering and Design
- Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor
- Annals of Nuclear Energy
- Loading pattern optimization of a PWR reactor fuel assemblies using PESA-II algorithm by considering neutronic and thermal-hydraulic parameters
- علوم و فنون هسته اي
- The station blackout accident in a dual-cooled annular fuel of a VVER-1000 reactor with application of portable pumps for mitigating the accident
- Annals of Nuclear Energy
- Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
- Nuclear Engineering and Technology
- Effects of the move towards Gen IV reactors in capacity expansion planning by total generation cost and environmental impact optimization
- Nuclear Engineering and Technology
- Study the effects of various parameters on hydrogen production in the WWER1000/V446
- Progress in Nuclear Energy
- Development of the triangle-based nodal algorithm for reconstructing pin power distributions
- Progress in Nuclear Energy
- Accurate full superfine group resonance self-shielding method with fission source and upscattering effects in thermal lattice
- Annals of Nuclear Energy
- The ?-synthesis and analysis of water level control in steam generators
- Nuclear Engineering and Technology
- Fractional order PID control of steam generator water level for nuclear steam supply systems
- Nuclear Engineering and Design
- Comparison of multi-point kinetics method with neutron diffusion equation and common point kinetics to investigate transient behavior in reactors
- فناوري و انرژي هسته اي
- Application of h -adaptivity to the interface current collision probability method
- Annals of Nuclear Energy
- Physical probability table applied to response matrix-collision probability method for direct whole-core transport calculations
- Annals of Nuclear Energy
- Hybrid space-angle adaptivity for whole-core particle transport calculations
- Annals of Nuclear Energy
- An adaptive node refinement for particle transport techniques based on response matrix and collision probability methods
- Annals of Nuclear Energy
Conferences Articles
- Bi-Level Network Reconfiguration Model to Enhance the Resilience of Distribution Systems Considering Risk-Based INDEX
- دانشگاه تبريز
- Optimization of the biological shield of a typical modular reactor
- انجمن علمي حفاظت در برابر اشعه ايران
- future studies of factors affecting the growth of scientific products in the field of nuclear science and technology
- دانشگاه خوارزمي
- Water level and pressure control in pressurized light water reactor pressurizer using fractional order method
- بيست و نهمين کنفرانس ملي هستهاي ايران
- The loss of coolant flow accident in a VVER-1000 reactor using coupled PARCS and RELAP5/MOD3.3
- بيست و نهمين کنفرانس ملي هستهاي ايران
- Reliability evaluation of wind-pv-battery with probabilistic models
- هشتمين همايش ملي مطالعات و تحقيقات نوين در حوزه علوم كامپيوتر برق و مكانيك ايران
- Reliability evaluation of micro-grids with probabilistic modeling of battery energy storage systems
- ششمين همايش بين المللي مهندسي برق علوم كامپيوتر و فناوري اطلاعات
- Reliability evaluation of micro-grids with probabilistic modeling of battery energy storage systems
- ششمين همايش بين المللي مهندسي برق علوم کامپيوتر و فناوري اطلاعات
- Reliability evaluation of wind-pv-battery with probabilistic models
- هشتمين کنفرانس بين المللي مهندسي برق، کامپيوتر و مکانيک
- disadvantage factor computation using collision probability in annular geometry
- کنفرانس هسته اي ايران
- thermo mechanical modelling of fuel rod in Bushehr Nuclear reactor in first cycle after startup using FRAPCON-3
- کنفرانس هسته اي ايران
Thesis
- Evaluating the reliability of microgrids using probabilistic modeling of energy storage batteries
- 1401/04/29 Omid Safarzadeh (استاد راهنما دوم)
- Multicopter’s Sound Source Separation from other Sound Sources
- 1400/11/09 Omid Safarzadeh (استاد راهنما 2)
- Optimization of biological shield of SMART modular reactor using PSO method based on modern materials
- 1400/10/22 Omid Safarzadeh (استاد راهنما 2)
- Pressure and water level control of reactor pressurizer using a three region model and fractional order method
- 1400/06/18 Omid Safarzadeh (استاد راهنما 1)
- Design of robust controller for small modular reactor (SMR)
- 1400/06/18 Omid Safarzadeh (استاد راهنما 1)
- Design of power control system using fuzzy-PID control and PSO, GA and GWO algorithms for nuclear power generation system in space based on Stirling engine
- 1400/06/15 Omid Safarzadeh (استاد راهنما 1)
- Bi-level network reconfiguration model to enhance the resilience of distribution systems considering risk-based index
- 1400/06/15 Omid Safarzadeh (استاد راهنما 1)
- Provide an optimal method for the network restoration after blackout
- 1400/06/14 Omid Safarzadeh (استاد راهنما 1)
- Provide an optimal method for the network restoration after blackout
- 1400/06/14 Omid Safarzadeh (استاد راهنما 1)
- Modeling the use of advanced accumulator in the LOCA accident of the VVER-1000 nuclear power plant
- 1399/07/29 Omid Safarzadeh (استاد مشاور)
- Diesel generator start-up simulation during power outage (LOOP) to supply internal power consumption of a power plant using ETAP
- 1399/06/10 Omid Safarzadeh (استاد راهنما 1)
- Improve the dynamic performance of a power plants auxiliary power grid during starting a large induction motor using SVC
- 1399/06/10 Omid Safarzadeh (استاد راهنما 1)
- Investigation of reactor core behavior due to change of clad material feom Zircaloy to SiC and FeCrAl
- 1399/04/02 Omid Safarzadeh (استاد راهنما 2)
- Optimization of Nuclear Reactor Core Configuration with Considering Neutronic and Thermo-hydraulic Cost Function using PARCS code
- 1398/10/25 Omid Safarzadeh (استاد مشاور)
- Modeling of fuel burnup and power distribution calculation in the second cycle of Bushehr power plant
- 1398/06/17 Omid Safarzadeh (استاد راهنما 2)
- Determination of optimum investment strategy in power plant sector of Iran
- 1398/06/11 Omid Safarzadeh (استاد راهنما 1)
- Investigation of the effect of using mobile equipment on heat extraction from the heart of Bushehr reactor during SBO
- 1398/04/02 Omid Safarzadeh (استاد مشاور 1)
- 1397/06/14 Omid Safarzadeh (استاد راهنما دوم)
- Fractional control of water level in the nuclear steam generator
- 1397/04/25 Omid Safarzadeh (استاد راهنما دوم)
- Investigation of Large break loss of coolant accident (LBLOCA) in light water pressurized reactor using TRACE/PARCS Code with uncertainty and sensitivity analysis of main parameters
- 1396/06/15 Omid Safarzadeh (استاد راهنما دوم)