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درباره دانشکده
History
Faculty members
Achievements
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Faculty Members
ataollah rabiee
ataollah rabiee
(FA Page)
Associate Professor
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Articles And Books
Research Plans
Thesis
Offered Courses
Articles
ataollah rabiee،Mohamad Mehdi Alishahi،Homayoun Emdad ,A robust algorithm for computing fluid flows on highly ,Int. J. Numer. Meth. Fluids ,vol. 0 ,2009 ,pp. 1011-1033 ,
ataollah rabiee،Mohamad Mehdi Alishahi،Homayoun Emdad،Bahador Saranjam ,Experimental investigation of bounce phenomenon ,Scientia Iranica ,vol. 0 ,2011 ,pp. 416-422 ,
ataollah rabiee،Mohamad Mehdi Alishahi،Homayoun Emdad , Part BUMERICAL INVESTIGATION OF UNSTEADY SUPERCAVITATING FLOWS ,IJSTTransactions of Mechanical and Materials Engineering ,vol. 0 ,2011 ,pp. 167-182 ,
ataollah rabiee،Mohamad Mehdi Alishahi،Homayoun Emdad ,PART A EXPERIMENTAL INVESTIGATION OF UNSTEADY SUPERCAVITATING FLOWS ,IJST Transactions of Mechanical and Materials Engineering ,vol. 0 ,2011 ,pp. 15-29 ,
Mohammadhadi Porhemmat،Farshad Faghihi،ataollah rabiee ,Primary loop analysis for a modern PWR contains passive core cooling systems; LOCA and clad rising temperature ,Annals of Nuclear Energy ,vol. 0 ,2015 ,pp. 8-21 ,
K Hadad،aref rahimian،ataollah rabiee ,Nanofluid Application in Post LOCA Transient in VVER-1000 NPP ,Annals of Nuclear Energy ,vol. 0 ,2015 ,pp. 101-110 ,
Mohammad Mehdi Mohammadi،Farshad Faghihi،Ahmad Pirouzmand،ataollah rabiee ,Study on the recently proposed direct S-Co2 and helium-cooled GCFR Size of vessel Power Conversion and reactivity coefficients ,Progress in Nuclear Energy ,vol. 0 ,2015 ,pp. 113-122 ,
ataollah rabiee،Alireza Atf ,Three-D numerical investigation of water/CuO nanofluid critical heat flux phenomenon in a PWR core channel during LOCA ,Progress in Nuclear Energy ,vol. 0 ,2015 ,pp. 228-238 ,
ataollah rabiee،Alireza Atf ,A Numerical Assessment of Copper oxide and Alumina Nanoparticles during CHF Occurrence ,Progress in Nuclear Energy ,vol. 0 ,2015 ,pp. 121-129 ,
Mohammadhadi Porhemmat،Farshad Faghihi،ataollah rabiee ,A reduced model for modern PWR primary loop Part I RELAP benchmarking ,Int. J. Nuclear Energy Science and Technology ,vol. 0 ,2015 ,pp. 201-223 ,
Mohammadhadi Porhemmat،Farshad Faghihi،ataollah rabiee ,Primary loop analysis for a PWR contains passive core cooling system; LOCA and clad rising temperature ,Annals of Nuclear Energy ,vol. 0 ,2016 ,pp. 8-21 ,
ataollah rabiee،Alireza Atf ,Control rod drop hydrodynamic analysis for a pressurized water reactor ,Progress in Nuclear Energy ,vol. 0 ,2016 ,pp. 191-197 ,
ataollah rabiee،Amir Hossein Kamalinia،K Hadad ,Horizontal Steam Generator Thermal Hydraulic Simulation in Typical Steady and Transient Conditions ,Nuclear Engineering and Design ,vol. 0 ,2016 ,pp. 465-475 ,
ataollah rabiee،Amir Hossein Kamalinia،K Hadad , Two-Phase Flow Field Simulation of Horizontal Steam Generators ,Nuclear Engineering and Technology ,vol. 0 ,2016 ,pp. 99-99 ,
ataollah rabiee،mohammad mehdi mirzaee،M.R. Nematollahi،Alireza Atf ,Experimental and numerical investigation of natural circulation stability of the SHUNCL thermal-hydraulic loop ,Progress in Nuclear Energy ,vol. 0 ,2016 ,pp. 386-396 ,
ataollah rabiee،Amir Hossein Kamalinia،K Hadad ,Two Phase flow field simulation of horizonla steam generators ,Nuclear Engineering and Technology ,vol. 0 ,2017 ,pp. 92-102 ,
ataollah rabiee،Amir Hossein Kamalinia،K Hadad ,Two-Phase Flow Field Simulation of Horizontal Steam Generators ,Nuclear Engineering and Technology ,vol. 0 ,2017 ,pp. 92-102 ,
ataollah rabiee،Alireza Atf ,A computational fluid dynamics investigation of various nanofluids in a boiling flow field ,Progress in Nuclear Energy ,vol. 0 ,2017 ,pp. 61-69 ,
ataollah rabiee،Alireza Atf , Numerical Investigation of Water/AL_2 O_3 Nanofluid Dryout Phenomenon in a Vertical Channel ,Amirkabir Journal of Mechanical Engineering ,vol. 0 ,2019 ,pp. 25-32 ,
Hassan Saadati،K Hadad،ataollah rabiee ,Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid ,Nuclear Engineering and Technology ,vol. 0 ,2018 ,pp. 639-647 ,
ataollah rabiee،Alireza Atf ,Simulation of nanofluid dryout phenomenon in a PWR rod bundle with mixing vanes using computational fluid dynamics ,Progress in Nuclear Energy ,vol. 0 ,2018 ,pp. 270-279 ,
Masoud Ahmadi،Ahmad Pirouzmand،ataollah rabiee ,Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life ,Nuclear Engineering and Technology ,vol. 0 ,2018 ,pp. 1037-1042 ,
ataollah rabiee،Leila Moradi،Alireza Atf ,Numerical Analysis of Critical Heat Flux Phenomenon in a Nuclear Power Plant Core Channel in the Presence of Mixing Vanes ,Aut Journal Of Mechanical Engineering ,vol. 0 ,2017 ,pp. 119-130 ,
،Tooraj Nazari،ataollah rabiee ,Total loss of feedwater accident for VVER-1000/V446 NPP with operator action ,International Journal of Nuclear Energy Science and Technology ,vol. 0 ,2018 ,pp. 351-0 ,
Tooraj Nazari،ataollah rabiee،Hossein Kazeminejad ,Numerical investigation of the modal characteristics for a VVER-1000 fuel assembly ,Nuclear Engineering and Design ,vol. 0 ,2019 ,pp. 1-6 ,
Tooraj Nazari،ataollah rabiee،Hossein Kazeminejad ,Two-way fluid-structure interaction simulation for steady-state vibration of a slender rod using URANS and LES turbulence models ,Nuclear Engineering and Technology ,vol. 0 ,2019 ,pp. 573-578 ,
Masoud Ahmadi،ataollah rabiee،Ahmad Pirouzmand ,Development of a 3D thermohydraulic-neutronic coupling model for accident analysis in research miniature neutron source reactor (MNSR) ,Nuclear Engineering and Technology ,vol. 0 ,2019 ,pp. 1776-1783 ,
Ghasem Rahimi،M.R. Nematollahi،K Hadad،ataollah rabiee ,Conceptual design of a high neutron flux research reactor core with low enriched uranium fuel and low plutonium production ,Nuclear Engineering and Technology ,vol. 0 ,2020 ,pp. 499-507 ,
Mohsen Ebrahimian shams abad،Ahmad Pirouzmand،ataollah rabiee ,Time-invariant reliability assessment for a passive heat removal system based on FORM methodology with a new approach for finding the design point ,Annals of Nuclear Energy ,vol. 0 ,2020 ,pp. 107740-0 ,
Mirmahdi Hosseini،Farshad Faghihi،Ahmad Pirouzmand،ataollah rabiee ,Innovative passive management of the Station Black-Out accident for VVER1000/V446 NPP and development of its emergency operating procedures ,Progress in Nuclear Energy ,vol. 0 ,2020 ,pp. 103416-0 ,
Ali Fakhraei،Farshad Faghihi،ataollah rabiee،Mohsen Safarinia ,Coolant flow rate instability during extended station blackout accident in NuScale SMR Two approaches for improving flow stability ,Progress in Nuclear Energy ,vol. 0 ,2021 ,pp. 103602-0 ,
Behzad Salmassian،ataollah rabiee ,The-Risk-Assessment-of-Cancer-Risk-during-Normal-Operation-of-Tehran-Research-Reactor-Due-to-Radioactive-Gas-Emission ,International Journal of Medical and Health Sciences ,vol. 0 ,2019 ,pp. 274-278 ,
Tooraj Nazari،ataollah rabiee، ,Flow-induced vibration analysis of nuclear fuel rods using equivalent fuel element model ,Nuclear Engineering and Design ,vol. 0 ,2020 ,pp. 110639-0 ,
Hamidreza Mohammadi،Hamed Taghvaei،ataollah rabiee ,Plasma deposition of a stable SiO x ?like layer on copper surface for enhanced pool boiling heat transfer performance A combination of microstructures and wetting properties ,Plasma Processes and Polymers ,vol. 0 ,2021 ,pp. 0-0 ,
Hassan Saadati،K Hadad،ataollah rabiee،Amir Hossein Kamalinia ,Evaluation of nanofluid coolant effects on VVER-1000/V-446 reactor using 3-D full core coupled neutronic and thermohydraulics analysis ,Annals of Nuclear Energy ,vol. 0 ,2021 ,pp. 107995-0 ,
Behzad Salmassian،ataollah rabiee،M.R. Nematollahi،Farshad Faghihi،Ahmad Pirouzmand ,Transient Parameter Analysis of Non-scrammed Local Melting Accidents—A VVER 1000 Case Study ,Frontiers in Energy Research ,vol. 0 ,2021 ,pp. 0-0 ,
Mohsen Ebrahimian shams abad،Ahmad Pirouzmand،ataollah rabiee ,Developing a method for time-variant reliability assessment of passive heat removal systems in nuclear power plants ,Annals of Nuclear Energy ,vol. 0 ,2021 ,pp. 108365-0 ,
Farhad Salari،ataollah rabiee،Farshad Faghihi ,Investigation of ex-vessel core catcher for SBO accident in VVER-1000/V528 containment using MELCOR code ,Nuclear Science and Techniques ,vol. 0 ,2021 ,pp. 0-0 ,
Hamidreza Mohammadi،Hamed Taghvaei،ataollah rabiee ,Experimental study of pool boiling on hydrophilic and hydrophobic thin films deposited on copper surfaces using atmospheric cold plasma ,International Journal of Thermal Sciences ,vol. 0 ,2022 ,pp. 107474-0 ,
Farhad Salari،ataollah rabiee،Farshad Faghihi ,Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents ,Nuclear Engineering and Technology ,vol. 0 ,2023 ,pp. 144-155 ,
Sahar Ghaseminejad،K Hadad،hadi porhemmat،ataollah rabiee ,Evaluation of time dependent neutron transport algorithms using 2D modular ray tracing MOC ,Progress in Nuclear Energy ,vol. 0 ,2023 ,pp. 104833-0 ,
Amir Hossein Kamalinia،ataollah rabiee ,Degradation analysis of horizontal steam generator tube bundles through crack growth due to two-phase flow induced vibration ,Nuclear Engineering and Technology ,vol. 0 ,2023 ,pp. 0-0 ,
Behzad Salmassian،ataollah rabiee،M.R. Nematollahi،Ahmad Pirouzmand ,Diagnosing core local flow blockages in a VVER-1000/446 reactor using ex-core detectors and neural networks ,Progress in Nuclear Energy ,vol. 0 ,2023 ,pp. 104736-0 ,
ataollah rabiee،Alireza Atf،Amir Hossein Kamalinia ,Numerical investigation of Al2O3 nanoparticle effect on a boiling forced swirl flow field application to the ITER project ,International Journal of Nuclear Energy Science and Technology ,vol. 0 ,2020 ,pp. 114-132 ,
Ali Fakhraei،Farshad Faghihi،Mohsen Mohammadi،ataollah rabiee ,DYSN Dynamics simulator for the NuScale SMR - A mathematical framework for transient analysis ,Progress in Nuclear Energy ,vol. 0 ,2024 ,pp. 105128-0 ,
Conferences
ataollah rabiee،Mohamad Mehdi Alishahi ,Experimental and Numerical Investigation of Sphere Impact Problem ,ISME2010 ,
ataollah rabiee،Mohamad Mehdi Alishahi،Homayoun Emdad , بررسی آزمایشگاهی مساله بلند شدن از روی آب برای مدل با سر مخروطی ,نهمین کنفرانس انجمن هوافضای ایران ,
Omid Abouali،ataollah rabiee ,Computational Simulation of supersonic Flow Using Reynolds Stress Mode- ,ASME Fluids ,
Zahra Karamimehr،ataollah rabiee ,Computing flows on highly non-smooth staggerd grids ,12th Asian Congress on Fluid Mechanics (12ACFM) ,
ataollah rabiee،Mohammad Reza Alizadeh،Mohamad Mehdi Alishahi ,NUMERICAL AND EXPERIMENTAL INVESTIGATION OF A WATER ENTRY PROBLEM WITH IMPACT EFFECTS ,دینامیک شاره ها ,
ataollah rabiee،Mohammad Abbaszadeh ,Comparison of ALE and FVM approaches for the solution of water entry problem , چهارمین کنفرانس ملی و دومین کنفرانس بین الملی پژوهش های کاربردی در مهندسی برق، مکانیک و مکاترونیک ,
ataollah rabiee،K Hadad،Hassan Saadati ,Evaluation of Nanofluid Coolant Effects on Safety margins and Fuel cycle Period of VVER-1000 Reactor ,5th International Reliability and Safety Engineering Conference ,
Mohsen Ebrahimian shams abad،ataollah rabiee،Ahmad Pirouzmand ,The Effect of Thermal Conductivity on the Central Temperature Safety Criteria in a Typical WWER-1000 Nuclear Reactor ,5th International Reliability and Safety Engineering Conference ,
ataollah rabiee،Amir Hossein Kamalinia،Alireza Atf ,Safety Assessment of Swirl Boiling Flow ,5th International Reliability and Safety Engineering Conference ,
Mohsen Ebrahimian shams abad،Ahmad Pirouzmand،ataollah rabiee ,ارزیابی قابلیت اطمینان متغیر با زمان سیستم غیر فعال برداشت حرارت راکتور VVER ,IRSEC2020 ,
K Hadad،ataollah rabiee،Mansour Kanani،Mohammad Shahrnaz kian ,Molecular dynamics simulation of neutron irradiation damage in Aluminum alloy used in Isfahan Research Reactor vessel ,6th International Reliability and Safety Engineering Conference ,
Ebrahim Ghanbari،ataollah rabiee،M.R. Nematollahi ,IDPSA to Decrease Risk & Energy Consumption in a Typical PWR ,IRSEC2020 6th International Reliability and Safety Engineering Conference ,
Fundamentals
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FirstName And Last Name
Project Name
Degree
download-thesis
def-date
Ali Abrar
Numerical investigation of the boiling phenomenon of two successive droplets impacting on an oblique hot solid surface
M.S
1397/11/30
Masoud Ahmadi
Development and validation of a Neutronic-Thermohydraulic coupling model using experimental data of Isfahan Miniature Neutron Source Reactor (MNSR) for accident analysis in research reactors
Ph.D
1398/04/30
Alireza Atf
Thermo-hydraulic Analysis of Dryout Phenomenon in a Boiling Channel with the Injection of Nano Particle Al2O3
M.S
1393/12/19
hamid azarbad
Ph.D
sajjad bahar
Estimation of Corrosion in Insulated Pipes with Using Simulation of Gamma Ray Back Scattering Method
M.S
1400/06/31
maryam bordbar
Prompt gamma imaging for in vivo range verification of projectile particles of pencil beam scanning ion therapy in the presence of a magnetic field
M.S
1400/06/31
mohsen Ebrahimian shams abad
Time-Variant Reliability Assessment of Passive Heat Removal System (PHRS) in VVER
Ph.D
1399/10/24
Ebrahim Ghanbari
The Analysis of Operator Performance in Feed and Bleed Process to Reduce the Risk of Station Blackout Accident of a Typical Pressurized Water Reactor
M.S
1397/06/31
Sahar Ghaseminejad
The Development of a Time-Dependent Neutron Transport Solution by Method of Characteristics in 2D Utilizing Modular Ray Tracing
Ph.D
1401/11/15
Mohammad Irvani
Basic design of a self-contained long life SMR reactor
M.S
1397/06/31
Mahdi Izadi
Film thickness measurement in annular gas-liquid two-phase flow through large-diameter vertical pipes using dual gamma transmission and scattering modality
M.S
1399/06/31
Amir Hossein Kamalinia
Degradation analysis of horizontal steam generator tube bundles through crack growth due to two-phase flow induced vibration
Ph.D
1402/06/29
Amir Hossein Kamalinia
Thermal-Hydraulic Simulation of Horizontal Steam Generators During Normal and Transient Operational Conditions
M.S
1394/06/30
Zahra Karamimehr
Sensivity Analysis on Operator Action in Main Steam Line Break Followed by Total Loss of Steam Generator Feed Water in VVER-1000/V446 Nuclear Reactor
M.S
1397/06/26
ali karimitalab
Examination of Fission Fragments Release and Thermomechanical Analysis of a VVER-1000 Nuclear Reactor Fuel Rod using FRAPCON code
M.S
1400/06/31
Sara Masjedian jazi
In-core neutron and gamma monitoring of Bushehr nuclear reactor
M.S
1395/09/17
mohammad mehdi mirzaee
Simulation of SHUNCL Natural Circulation Loop Using RELAP5 code and Compare its Results with Experimental data
M.S
1393/11/19
Hamidreza Mohammadi
Experimental study of pool boiling parameters using plasma coating on a hot surface
M.S
1399/06/23
Leila Moradi
DNB Analysis of a Hot Channel with Grid Spacer and Mixing Vanes in Presence of Nanofluid Coolant
M.S
1395/06/08
elham narooi
The termohydrolic analysis of cooling ITER reactor's divertor by using swirl flow
M.S
1392/12/03
zahra nasimi
Investigation of fluid-structural interaction of fuel rods using one-way coupling approach
M.S
1401/06/31
Tooraj Nazari
Numerical Analysis of the Axial-Flow-Induced Vibration in TVS-2 Fuel Assemblies
Ph.D
1397/11/30
Narsis Nejat
Conceptual design on the fuel of RTG for in-planets space traveling
M.S
1392/09/30
Ahmad Ramezani
The Investigation of Operator Action in Process of Total Loss of Steam Generator Feed Water Accident in Bushehr NPP
M.S
1395/11/25
Hassan Saadati
Neutronics & thermo-hydraulics analysis of nano-fluid as coolant & reactivity controller in the first operating cycle of BNPP
M.S
1395/11/13
Najmeh Sadamehdar
Experimental investigation of radioactive iodine leaching in a calcareous soil treated by bagasse derived biochar
M.S
1397/11/23
farhad salari
Assessment of the core corium catcher safety system for typical VVER-1000 nuclear reactor during severe accidents
Ph.D
1400/06/31
behzad salmasian
The VVER-1000/446 core blockage location diagnosis using neutron detectors and neural networks
Ph.D
1400/06/31
Ali Shahabinejad
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code
M.S
1398/06/31
Mohammad Shahrnaz kian
Molecular dynamics simulation of neutron irradiation damage in Aluminum alloy used in Isfahan Research Reactor vessel.
M.S
1399/06/31
abolfazl zarei
Sensitivity Analysis on Operator Action in Steam Generator Tube Rupture Accident Followed by Main Steam Line Break in VVER-1000/V446 Nuclear Reactor
M.S
1399/06/31
tara zarekarasadi
Development of a muon radiography system to measure the thickness change of FAC-induced pipes by the Monte Carlo method
M.S
1400/11/15
rasmieh zeynavimayanabi
Scale Measurement in Thick Hydrocarbon Flow Pipeline by Hybrid Multi-beam Gamma-ray Technique and Artificial Neural Network
M.S
1400/11/15
marzieh ahmadi jame bozorgi
Radiation detection and dosimetry using smartphone image sensor
M.S
1402/11/15
mostafa amiri bahmanbiglo
Numerical analysis of CCFL phenomenon for hot leg of Bushehr power plant and test facility on a scale of 1/19 to optimize dimensions of test facility
M.S
elahe esmaeili
Prediction of porosity, permeability and water saturation of gas reservoirs using nuclear logs with machine learning
M.S
1402/12/16
Maryamsadat Hosseini
Reliability Analysis of Digital Protection System of a typical Research Reactor Using Dynamic Flowgraph Methodology (DFM)
M.S
1402/06/27
Mohammad Khalvandi
Ph.D
mohammad mansourimanesh
Numerical investigation of the stress field created in the pressurizer of Bushehr nuclear power plant unit-1 due the emergency shutdown
M.S
1402/12/05
Fatemeh Roosta
Developing dynamic event tree for SGTR accident in unit 1 BNPP
Ph.D
sanaz sadinia
Development of a Muography System for Prospecting and Exploration of Metallic Anomalies of Mineral Resources
M.S
1402/12/15
habibullah sharifi
Measurement of radon gas concentration and estimation of effective dose in residential houses of Kabul city, Afghanistan
M.S
saied soltanmohammadi
Assessment of VVER-1000/V446 nuclear power plant containment integrity against the hydrogen explosion risk under sever accidents
Ph.D
Atoosa Zahedi ghadi
Numerical simulation of fire phenomenon in Bushehr nuclear power plant control room and analysis of aerosol distribution and fire pollutants to the surrounding environment using FDS field code
M.S
1401/06/30
ERFAN ZIYADI
Investigating The Increase Of Heat Transfer In The Pool Boiling Regime By Considering Nanoparticles/Microparticles And Layering On The Metal Surface
M.S
1402/12/13
negin afshar
Probabilistic and Deterministic Safety Assessment of VVER-1000/V446 Reactor's Spent Fuel Pool to Calculate Fuel Damage Frequency (FDF)”
Ph.D
1400/06/31
Aliakbar Bahrami Dehtuti
VVERs design basis using the Accident Tolerance Fuels (ATF) loading based on the PARCS-RELAP5 coupling and for a few transient cases
Ph.D
sohrab barzegar
Development of RELAP5 Model CAREM-25 Reactor to Analyze the Reactor Safety During the Control Rod Ejection Accident
M.S
1401/06/31
mohsen dehghan
Numerical Study of Flow Field Downstream of Typical Orifice in Power Plants by CFD Method
M.S
Ali Fakhraei
Development of NuScale Small Modular Reactor RELAP5 Model for Safety Analysis of the Reactor in the Station Blackout Accident.
M.S
1396/06/29
ali fakhraei
Dynamics stability analysis of a passively cooled IPWR and design of controller system for load following operation
Ph.D
1402/11/28
Saeid Ghaemi
Improvement of the VVER-1000 core using new type of fuel assembly (TVS-2M), and analysis the neutronic parameters at the steady and transient states.
Ph.D
1396/12/16
Zeynab Ghaemi
Effect of Ozonation on Water Quality and Simulation of Ozone Dispersion in Water Using Computational Fluid Dynamics
M.S
1398/06/24
Reza Haghjoo Jahromi
A comparison of nuclear fuel cycle and operational cost between the HTGCFR and a Similar 1000 Mwe PWR
M.S
1391/12/15
zahra hasiri
Source term determination for accidents in the spent fuel pool of Bushehr nuclear power plant unit-1 using MELCOR code
M.S
1401/11/15
Mirmahdi Hosseini
development of the VVER-1000/V446 EOPs FOR the STATION black-out(SBO) Accident considering the deaerator tank and its validation using relap 5 code
Ph.D
1399/06/30
Masoud Jabary
Station black out accident scenario preparation for implementation of stress test program in Bushehr NPP
Ph.D
1398/06/31
morteza kazem dehdashti
VVER-1000 Reactor Core Monitoring by Ex-Core Neutron Detector and Artificial Neural Network (ANN)
M.S
1393/06/31
Mohammad Mehdi Mohammadi
Calculation of Temperature Coefficients of a Gas Cooled Fast Breeder Reactor
M.S
1393/06/26
Vahed Moharramzadeh
Magnetic Hyperthermia Using Magnetic Nanoparticles: An Applicator Development and the Treatment Planning Optimization for Combination of Hyperthermia with the Intraoperative Radiation Therapy (IORT)
Ph.D
1396/11/25
Yousef Mohseni
Analysis of Flow Accelerated Corrosion Downstream of Orifices in the Nuclear Power Plant Piping System
M.S
1400/06/31
Bahman Nazari
Analysis and construction of a hot rod with a sinusoidal heat production to simulate a nuclear fuel rod
M.S
1397/06/31
aref rahimian
Investigation of single and two-phase turbulent forced convection flow models of water/Al2o3 nano fluid in VVER-1000 nuclear reactor
M.S
1392/06/26
Ghasem Rahimi
Neutronic - thermal hydraulic Conceptual design of a medium-power research reactor core with low plutonium production and high neutron flux characteristics
Ph.D
1398/06/30
mohamad rashidi toghroljerdi
Simulation of Sphere Packed Pipe (SPP) Using Computational Fluid Dynamics
M.S
1393/03/11
jamshid rezaei abgoli
Evaluation of the spray system ability to remove radioactive material and reduce containment pressure during severe accident of VVER-1000/V446 nuclear power plant using MELCOR code
M.S
1398/06/27
Bahareh Sabetan
Design and Impelentation of a radon monitoring system using photo diod BPW34 and transferring data with GSM system
M.S
1393/06/31
Seyed Ehsan Saeidi
Calculation of the control rod worth of VVER-1000 core including TVS-2M fuel assemblies at the beginning of cycle
M.S
1402/06/13
Abbas Sedghkerdar
NUMERICAL AND EXPERIMENTAL ANALYSIS OF HYDRODYNAMIC PARAMETERS EFFEC ON FLOW ACCELERATED CORROSION AT THE DOWNSTREAM OF A GATE VALVE APPLIED TO A TYPICAL SYSTEM FAILURE EVALUATION
Ph.D
1399/06/01
Hasan Shakouri
Numerical simulation and laboratory evaluation of a sprayer T-jet nozzle flow
M.S
1397/11/30
Saied Soltanmohammadi
Analysis of VVER-1000/V446 Reactor Containment Behavior During Severe Accident Conditions Using MELCOR Code
M.S
1397/06/24
poria soroush
Turbulence flow simulation on AP-1400 fuel assembly by CFD method
M.S
1392/12/19
samad tayyebi khorrami
Simulation of Rough Rice Drying in a Laboratory-Scale Ultrasound-assisted Fluidized Bed Dryer Using CFD Method
M.S
1396/11/15
AmirAli Bonyadi
CFD analysis of spacer grids effects on heat transfer, pressure drop and fluctuations of thermohydraulic parameters in a typical research reactor with an annular fuel assembly
M.S
1402/04/10
mohamad hasan dehghani
Damage assessment of VVER1000 fuel rod in the case of normal startup and a typical DBA accident using FRAPTRAN code
M.S
1402/06/11
MOHAMMAD JAVAD KHALEGHI
CFD Simulation of Onset of Nucleate Boiling on a Heated Rod With Sinusoidal Heat Generation
M.S
Maryam Mohammadi
Development of an Emergency Dispersion Model of Conservative Radionuclides in Coastal Water of Persian Gulf Using Coupling of Transport and Hydrodynamic Models
Ph.D
Hamidreza Momtaz
Simulation and Analysis of Fire Accident in a Typical Nuclear Fuel Production Complex Based on Computational Fluid Dynamics, and Two-Zone Models
M.S
1402/12/16
Elaheh Montazeri
Developing NuScale Reactor Steam Generator Dynamics Model based on Artificial Neural Networks
M.S
1402/06/18
Zeinab Motevalli Bashi Naini
Identification of Scale Deposition in Oil Pipelines by Gamma Computed Tomography (GCT)
M.S
Seyed Abolhasan Nabavi Chashmi
Developing a Model for Assessment of Dose Distribution Around BNPP-1 Due to Severe Accidents Using Dynamic Event Tree and Deep Learning
Ph.D
Masomeh Sharifi por Shirazi
Chemical spectral shift control method applied to VVER-1000/446
M.S
1402/12/16
Arefoddin Zarnousheh Farahani
Analysis of In-Vessel Melt Retention Strategy by External Cooling for a Typical Pressurized Water Reactor and Evaluating its Effective Parameters on Severe Accident Management
Ph.D
Ehsan Aalaei
Design, Numerical Simulation and Optimization of a Concentration Gradient Generator for Drug Screening
M.S
1399/06/31
roozbeh aayani
Experimental study of a propeller hydrodynamic noise
M.S
1391/07/12
Mehrab Abbasi
Experimental analysis of the pressure drop in human nasal cavity before and after maxillary antrostomy
M.S
1400/06/31
arash abbaszadeh
Safety analysis of Bushehr nuclear power plant unit-1 against loop accident with main steam line break using the RELAP5 code
M.S
1399/11/30
Behrooz Ahmadi
Experimental study of natural convective dehumidification from humid air on square fin arrays
M.S
1397/06/31
POUYAN AHMADI
Recovery curve generation of Co-current and Counter current imbibition by experimentally investigations
M.S
1396/06/31
Mahboubeh Amouzgar
Study of structure and heat transfer characteristics of turbulent flow over dimpled surface
M.S
1398/06/26
Ehsan Ardekani
Three-dimensional modeling of smoke due fire and smart extraction in a metro station
M.S
1396/06/31
Zahra Azizi
Uncertainty analysis of natural frequencies of nanoparticles and nanowires by using Monte Carlo method
M.S
1397/11/14
Ali Baghernejad
Thermoeconomic and environmental analysis for synthesis of trigeneration plants using organic fluids with fuel cell and renewable energy sources
Ph.D
1394/07/25
vahid bahmani
Failure analysis of a gas turbine first stage blade and its comparison with an upgraded model and industrial investigations
M.S
1397/11/30
Mohammad Bahmanpour
Dynamic modeling and optimization of an energy harvester with rack and pinion mechanism
M.S
1399/06/31
behnam behzadi nejad
The Feasibility Study of Using Nano-fluids as a Neutron Absorber in Reactor Emergency Core Cooling System
M.S
1392/12/20
zeynab dalir
Investigation of different human error models for CDF Evaluation for SBO accident management in VVER-1000 reactor using portable equipment
M.S
1400/06/31
Motahare Effati Kalarmi
Investigation on the improvement of the accuracy and speed in the neutron transport solution by method of characteristics applying the adaptive mesh refinement, convergence acceleration and parallelization
Ph.D
1398/06/31
Alireza Fath
Dynamic modeling and control of a tuned liquid column semi-submersible offshore wind turbine
M.S
1397/06/14
Nasiballah Fotovvatpour
Impact Analysis of Helmet' s Function using Finite Element Simulation of Skull and Helmet Containing Aluminum Foam
M.S
1398/06/27
ali ghasemi
Investigation of core meltdown phenomena and radioactive materials release in VVER-1000/V446 nuclear reactor at severe accident conditions due to LBLOCA
M.S
1394/12/19
Seyedeh narges Ghiasi shirazi
Identification of Intensity and Location of Point Heat Sources in Themoelasticity Problems Using an Improved Meshless Method and Search Algorithms
M.S
1395/12/18
Hooman Hadidi
Molecular Dynamics Investigation of Mutated Aquaporins and Biomimetic Membranes
Ph.D
1399/06/31
Danial Khojasteh
Dynamic modeling of a towed undersea body and dynamic study of a point absorber wave energy converter
M.S
1394/06/31
saeed khorsandi
Building Integrated Photovoltaic Thermal System Using Slotted Panels
M.S
1396/06/04
Salman Khoshnood
Modeling and optimization of a multiple-effect distillation system integrated with gas turbine to utilize waste exhaust gas
M.S
1396/06/29
Elham Khosrowpour
A strong-form meshless method for stress analysis of hyperelastic material
M.S
1397/02/29
Ahmad ali mahmoudi
Numerical Study of Fluid Structure Interaction Effect on Particle Transport and Deposition in The Realistic Human Lung Model
M.S
1393/12/20
Niloufar Manouchehri charamakani
Assessment of Proposed Sites for the Establishment of Fars Research Reactor
M.S
1398/06/31
Mohammad hosein Mashayekh
Numerical investigation on the effect of swirl number on the entropy waves in combustion chamber of SANDIA D
M.S
1400/04/10
Mohamad hadi Memardezfuli
Techno Economic and Environmental Analysis of Gas Combined Cycle, Gas with (ORC) and Gas With Solar and (ORC)
M.S
1397/11/30
Mohsen Mohammadi
Control and stability of nonlinear Itô stochastic micro systems
Ph.D
1396/06/20
mehdi mohammadi rahaghi
experimental study of liquid & sand erosion in pipe line
M.S
1393/12/19
Amirhossein Momeni
Investigation of variations in velocity field and heat transfer rate for incompressible fluid flow under external magnetic field in concentric annulus with effect of magnetic joule dissipation
M.S
1399/06/29
Leila Monajati
Linear and nonlinear vibrations analysis of FG plates based on improved refined shear and normal deformation theory using Airy stress function
M.S
1395/06/27
Ahmadreza Motaffef
Numerical Simulation of Contra-Rotating Propellers and Investigation of Geometry Changes on its Performance
M.S
1393/06/29
Mohamad Nazermozafary
Dynamic modeling and control of human lower limbs during walking considering both active and passive cross joint moments
M.S
1397/11/30
Mostafa Nejatolahi
Equilibrium versus Nonequilibrium Molecular Dynamics for Calculating the Thermal Conductivity of Nanofluids
Ph.D
1399/06/31
Mohammad ali Nematollahi
Modeling and dynamical behavior analysis of fluid-conveying micro-pipes in order to use in mass flow meters
M.S
1397/11/30
mahdi omidvar
Defect Detection of Aluminum Castings based on Analysis of Radiography Images using Deep Learning Combined with Data Augmentation by Generative Adversarial Networks
M.S
1400/06/31
Siyamak Parsaei
The use of multi-state physics modeling approach in the reliability assessment of steam generator tubes of ZION nuclear power plant
M.S
1396/06/28
Sahar Pourandi
Vibration Analysis of Circular Double-Layered and Rectangular Single-Layered Graphene Sheets Subjected to In-plane Magnetic Field
M.S
1396/12/19
nazanin rafiee bakhsh
Laminar free convective heat transfer from convex bodies with constant heat flux
M.S
1399/12/24
Majid Rafiei
Shape Optimization of Sections Under Torsion Using a Mesh Free Method
M.S
1397/06/31
SINA RASTEGARZADEH
Optimum Design of Multi-Ring Flywheel Energy Storage System with Magnetic- Mechanic Bearings for use of Energy Reduction in Light Metro Trains
M.S
1397/06/21
Vahid Rezaee
Numerical study on productivity of single basin solar still integrated with phase change material (PCM)
M.S
1399/11/30
Mohsen Safarinia
Secondary shutdown system design using heavy water tank in open pool research reactors
M.S
1393/09/25
sahba salarian
Numerical Simulation of Hybrid Electrokinetic Separation of Circulating Tumor Cells from Highly Conductive Biological Fluids
M.S
1394/03/26
Mohammad Salehi
Flexible multibody dynamic modeling and vibration analysis of a semi-submersible o?shore wind turbine
M.S
1398/11/28
Soheil Salighe
Designing a vibration absorber for a nonlinear system with uncertainty
M.S
1397/01/27
Ghazal Shammasi
Investigating the performance of Eulerian two-phase model in simulating laminar natural convection of nanofluids in square cavity
M.S
1398/11/30
سينا Sina
Numerical investigation of a microchannel heat sink under the influence of transversal electroosmotic flow
M.S
1398/11/30
Mohammadrez Zerehpoosh
Risk based assessment of AOT and STI for ECCS and EDGS systems of VVER-1000/446 nuclear reactor in LOCA accidents
M.S
1397/11/23
Ehsan Zolfaghari
Dynamic Modeling and Control of Human Lower Limb in Cycling
M.S
1398/06/31
پريسا اميدي فرد
Analysis of Severe Accident Sequences in the Spent Fuel Pool of the VVER-1000/V446 Nuclear Reactor
M.S
1397/06/27
عليرضا سنائي
Design, Dynamic Modeling and Control of a Lower-limb Rehabilitation Robot
M.S
1397/06/31
DSMC Simulation of Supersonic Impactors in Rarefied Conditions for Separation of Nanoparticles
Ph.D
1392/07/10
Uncertainty Analysis of Common Cause Failure Model Parameters and Assessment of their effects on CDF in LOCA Accidents
M.S
1397/11/21
Name
Advanced Numerical Calculations
Fundamentals of Thermo-Hydraulics
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