About Us

M.R. Nematollahi

M.R. Nematollahi (FA Page)

Professor

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Virtual Room : http://vroom.shirazu.ac.ir/nema

Articles

M.R. Nematollahi، ,A Simulation of a Steam Generator Tube Rupture in a VVER-1000 Plant ,Energy Conversion and Management ,vol. 0 ,2008 ,pp. 1972-1980 ,
M.R. Nematollahi، ,Development and application of a Risk Asswssment Tool ,Reliability Engineering & System Safety ,vol. 0 ,2008 ,pp. 1130-1137 ,
M.R. Nematollahi ,Evaluation of Exerting Force on the Heating Surface Due to Bubble Ebullition in Subcooled Flow Boiling ,International Journal of Mechanical and Mechatronics Engineering ,vol. 0 ,2008 ,pp. 676-683 ,
M.R. Nematollahi،Mohammad Nazififard، ،hidetoshi hashizome ,Efect of Bend Curvature Ratio on Flow Pattern at a Mixing Tee after a 90 Degree Bend ,International Journal of Engineering ,vol. 0 ,2009 ,pp. 1-6 ,
Saiedeh Safaei Arshi،M.R. Nematollahi،kamran sepanloo ,Coupling CFAST fire modeling and SAPHIRE Probabilistic assessment software for internal fire safety evaluation of a typical TRICA research reactor ,Reliability Engineering & System Safety ,vol. 0 ,2010 ,pp. 166-172 ,
M.R. Nematollahi،Mohammad Nazififard ,Evaluation of Heat Trans fer Shear of Different Mechanisms in Subcooled Nucieate Boiling ,international journal of engineering ,vol. 0 ,2010 ,pp. 1-6 ,
Kavoos Abbasi،nasrin hoseini motlagh،M.R. Nematollahi،hidetoshi hashizome ,Detection of axial crack in the bend region of a pipe by the high frequency electromagnetic waves ,International Journal of Pressure Vessels and Piping ,vol. 0 ,2009 ,pp. 764-768 ,
shahab addin kamyab،M.R. Nematollahi ,Evaluating the core damage frequency of a TRIGA research reactor using risk assessment tool software ,Nuclear Engineering and Design ,vol. 0 ,2011 ,pp. 2942-2947 ,
Zahra Tabadar،Kamal Hadad،M.R. Nematollahi،Mehdi Hashemi،Masoud Jabbari Dehaghi،Mohammad Khaleghi ,Simulation of a control rod ejection accident in a VVER-1000/V446 using ,Annals of Nuclear Energy ,vol. 0 ,2012 ,pp. 106-114 ,
shahab addin kamyab،M.R. Nematollahi ,Performance evaluating of the AP1000 passive safety systems for mitigation of small break loss of coolant accident using risk assessment tool-II software ,Nuclear Engineering and Design ,vol. 0 ,2012 ,pp. 32-40 ,
M.R. Nematollahi،babak khonsha ,Comparison of T-junction flow pattern of water and sodium for different geometries of power plant piping systems ,Annals of Nuclear Energy ,vol. 0 ,2012 ,pp. 83-93 ,
M.R. Nematollahi،mahdi rezaiean ,Failure Analysis of Low Pressure Evaporator Tubes in a Typical Combined Cycle Power Plant ,Applied Mechanics and Materials ,vol. 0 ,2012 ,pp. 4607-4614 ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y Suh ,NUMERICAL SIMULATION OF WATER BASED ALUMINA NANOFLUID IN SUBCHANNEL GEOMETRY ,Science and Technology of Nuclear Installations ,vol. 0 ,2012 ,pp. 1-12 ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y Suh ,Augmented Safety Heat Transport in Research Reactor IR-40 Using Nanofluid ,atw – International Journal for Nuclear Power ,vol. 0 ,2012 ,pp. 262-269 ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y. Suh ,Computational Analysis for Research Reactor IR-40 Rod Bundle ,atw-International Journal for Nuclear Power ,vol. 0 ,2012 ,pp. 523-529 ,
M.R. Nematollahi،Mohamadreza Mazhari ,QUANTITATIVE EVALUATION OF HEAT TRANSFER IN BUBBLE COLLAPSE PROCESS IN SUBCOOLED FLOW BOILING ,TRANSACTIONS OF FUSION SCIENCE AND TECHNOLOGY ,vol. 0 ,2012 ,pp. 186-192 ,
shahab addin kamyab،M.R. Nematollahi، ,Sensitivity analysis on the effect of software-induced common cause failure probability in the computer- based reactor trip system unavailability ,Annals of Nuclear Energy ,vol. 0 ,2013 ,pp. 294-303 ,
Kamal Hadad،aref rahimian،M.R. Nematollahi ,Numerical study of single and two-phase models of water/Al2O3 nanofluid turbulent forced convection flow in VVER-1000 nuclear reactor ,Annal of Nuclear Energy ,vol. 0 ,2013 ,pp. 287-294 ,
،M.R. Nematollahi،M. Hashemi Tilnouei ,Flow field analysis of BWRs’ liquid jet pump by FLUENT ,Iranian Journal of Nuclear Sciences and Engineering ,vol. 0 ,2013 ,pp. 27-36 ,
Mohammad Nazififard،poria soroush،M.R. Nematollahi ,HEAT TRANSFER AND SAFETY ENHANCEMENT ANALYSIS OF FUEL ASSEMBLY INADVANCED PRESSURIZED WATER REACTORS A CFD APPROACH ,Indian J.Sci.Res.1(2) ,vol. 0 ,2014 ,pp. 487-495 ,
Kamal Hadad،M.R. Nematollahi، ,VVER-1000 cross-section library generation for ORIGEN-II based on MCNP calculations ,International Journal of Hydrogen energy ,vol. 0 ,2015 ,pp. 15158-15163 ,
Ahmad Pirouzmand،peyman dehghani،Kamal Hadad،M.R. Nematollahi ,Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions ,International Journal of Hydrogen Energy ,vol. 0 ,2015 ,pp. 15199-15205 ,
Ahmad Pirouzmand،peyman dehghani،Kamal Hadad،M.R. Nematollahi ,Dose assessment of radionuclides dispersion from BNPP stack under normal operation and accident conditions ,journal of hydrogen energy ,vol. 0 ,2015 ,pp. 15198-15205 ,
Mahtab Adine،M.R. Nematollahi،Ali Erfaninia ,Experimental and numerical void fraction measurement for modeled two-phase flow inside a vertical pipe ,Annals of Nuclear Energy ,vol. 0 ,2015 ,pp. 188-192 ,
Reza Faghihi،M.R. Nematollahi،Ali Erfaninia،Mahtab Adine ,Void fraction measurement in modeled two-phase flow inside a vertical pipe by using polyethylene phantoms ,International Journal of Hydrogen Energy ,vol. 0 ,2015 ,pp. 15206-15212 ,
Shinji Ebaraa،M.R. Nematollahi،Hidetoshi Hashizume ,Visualization experiment of complex flow field in a sphere-packed pipe by detailed PIV measurement ,Fusion Engineering and Design ,vol. 0 ,2014 ,pp. 1251-1256 ,
M.R. Nematollahi،Ali Erfaninia،samira salatini ,REDUCTION OF CORE DAMAGE FREQUENCY VIA NEW DESIGN FOR EMERGENCY CORE COOLING SYSTEM IN A TYPICAL PWR will be published in ,International Journal of Hydrogen Energy ,vol. 0 ,2015 ,pp. 15185-15191 ,
M.R. Nematollahi،behnam behzadi nejad، ,Feasibility Study of Using Nano-Fluids as a Neutron Absorber in Reactor Emergency Core Cooling System ,International Journal of Hydrogen Energy ,vol. 0 ,2015 ,pp. 15192-15197 ,
Somayeh Bagheri،Farshad Faghihi،M.R. Nematollahi،behnam behzadi nejad ,Assessment of Thermal Hydraulics Parameters of the VVER-1000 During Transient Conditions ,Hydrogen Energy ,vol. 0 ,2016 ,pp. 7103-7111 ,
Kamal Hadad،hoda sadeghpour،M.R. Nematollahi ,Source substitution and optimization of CBX(TM) PGNAA analyzer in Kangan cement plant ,Progress in nuclear energy ,vol. 0 ,2016 ,pp. 204-211 ,
Mehdi Javidi،M.R. Nematollahi،Mohamad mehdi Lalehparvar،arash ghassemi ,Failure Analysis of AISI 321 Austenitic Stainless Steel Water Piping in a Power Plant ,Journal of Failure Analysis and Prevention ,vol. 0 ,2016 ,pp. 209-215 ,
Hamed Atajafari،M.R. Nematollahi،M. Hashemi Tilnouei، ,Validation of RELAP5/MOD3.2 Code for Flashing-Induced Instabilities in a Single Channel ,World Journal of Nuclear Science and Technology ,vol. 0 ,2015 ,pp. 6-17 ,
Ali Erfaninia،M.R. Nematollahi , Numerical study of mass transfer coefficient in a T-junction ,International Journal of Hydrogen Energy ,vol. 0 ,2016 ,pp. 7027-7035 ,
kourosh keshtkar،M.R. Nematollahi،Ali Erfaninia ,CFX study of flow accelerated corrosion via mass transfer coefficient calculation in a double elbow ,International Journal of Hydrogen Energy ,vol. 0 ,2016 ,pp. 7036-7046 ,
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 ,
Mahmood Yaghoubi، ،M.R. Nematollahi،Sajad Bashiry ,Experimental Study of Subcooled Pool Boiling around a Circular Rough Cylinder ,AUT Journal of Mechanical Engineering ,vol. 0 ,2017 ,pp. 21-28 ,
Ali Erfaninia،afshin hedayat،S. M. Mirvakili،M.R. Nematollahi ,Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX ,Progress in Nuclear Energy ,vol. 0 ,2017 ,pp. 213-227 ,
shahab addin kamyab،Kamal Hadad،M.R. Nematollahi ,Using MCNP for success criteria evaluation of reactor trip function in probabilistic modeling of ATWS upon LOOP ,Progress in Nuclear Energy ,vol. 0 ,2018 ,pp. 270-277 ,
Farshad Faghihi،Aliakbar Bahrami Dehtuti،M.R. Nematollahi،Afsane Mojassami ,A new fuel depletion code development for PWRs SUDEPLET code ,ANNALS OF NUCLEAR ENERGY ,vol. 0 ,2018 ,pp. 345-360 ,
shahab addin kamyab،M.R. Nematollahi،Faramarz Yosefpour،Kaveh Karimi،Shahabeddin Kamyab ,Investigating the effectiveness of outfitting nuclear power plant with automatic seismic trip system based on the early detection of earthquake ,Soil Dynamics and Earthquake Engineering ,vol. 0 ,2019 ,pp. 162-172 ,
Motahare Effati Kalarmi،Kamal Hadad،M.R. Nematollahi ,An accelerated synchronized forward-adjoint approach in method of characteristics neutron transport solution ,Annals of Nuclear Energy ,vol. 0 ,2019 ,pp. 820-829 ,
Ghasem Rahimi،Kamal Hadad،M.R. Nematollahi،Ehsan Zarifi،Sumer Sahin ,Comparison of semi-heavy water and H2O as coolant for a conceptual research reactor from the view point of neutronic parameters ,Progress in Nuclear Energy ,vol. 0 ,2020 ,pp. 103126-0 ,
Ghasem Rahimi،M.R. Nematollahi،Kamal 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 ,
Farshad Faghihi،Aliakbar Bahrami Dehtuti،M.R. Nematollahi،Afsane Mojassami ,A new fuel depletion code based on group-wise Bateman ODEs; SUDEPLET code for point-like PWR core ,Progress in Nuclear Energy ,vol. 0 ,2020 ,pp. 0-0 ,
babak khonsha،Gholamreza Jahanfarniaa،kamran sepanloo،M.R. Nematollahi ,Scaling and thermal-hydraulic design of a test loop for the VVER-1000 reactor ,Progress in Nuclear Energy ,vol. 0 ,2019 ,pp. 18-27 ,
Abbas Sedghkerdar،Ali Erfaninia،M.R. Nematollahi ,2D PIV study of flow accelerated corrosion downstream a typical industrial gate valve ,Progress in Nuclear Energy ,vol. 0 ,2020 ,pp. 103260-0 ,
Ghasem Rahimi،Kamal Hadad،M.R. Nematollahi ,Innovative designed fuel pin of conceptual semi-heavy water research reactor with improved reactor safety ,Progress in Nuclear Energy ,vol. 0 ,2020 ,pp. 103559-0 ,
shahab addin kamyab،M.R. Nematollahi،Pierre Henneuax،Pierre-Etienne Labeau ,Development of a hybrid method to assess grid-related LOOP scenarios for an NPP ,Reliability Engineering & System Safety ,vol. 0 ,2021 ,pp. 107298-0 ,
babak khonsha، ، ،M.R. Nematollahi ,Transient Thermal Hydraulic Analisis Of A Scaled Down Test Loopfore The Vver-100 Reactor Using RELAP5 Code ,ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER ,vol. 0 ,2020 ,pp. 595-602 ,
shahab addin kamyab،M.R. Nematollahi،Pierre Henneaux،Pierre-Etienne Labeau ,Investigating the influence of the variation of the load characteristic on the occurrence frequency of Grid-related Loss of Offsite Power using a probabilistic-deterministic methodology ,Progress in Nuclear Energy ,vol. 0 ,2021 ,pp. 103870-0 ,
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 ,
babak khonsha، ،kamran sepanloo،M.R. Nematollahi، ,ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant ,Kerntechnik ,vol. 0 ,2021 ,pp. 445-453 ,
Mohammadesmaeel Amirsoltani،Ahmad Pirouzmand،M.R. Nematollahi ,Development of a dynamic event tree (DET) to analyze SBO accident in VVER-1000/V446 nuclear reactor ,Annals of Nuclear Energy ,vol. 0 ,2022 ,pp. 108786-0 ,
Shahabeddin Kamyab، ،M.R. Nematollahi،Pierre Henneaux،Pierre-Etienne Labeau ,Assessment of the grid-related loss of offsite power to the nuclear power plants in the presence of wind farms ,Progress in Nuclear Energy ,vol. 0 ,2023 ,pp. 104508-0 ,
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 ,
Siyamak Parsaei،Ahmad Pirouzmand،M.R. Nematollahi،Ali Reza Ahmadi،Kamal Hadad ,Effect of test-caused degradation on the unavailability of standby safety components ,Nuclear Engineering and Technology ,vol. 0 ,2024 ,pp. 526-535 ,
Siyamak Parsaei،Ahmad Pirouzmand،M.R. Nematollahi،Ali Reza Ahmadi،Mohammad reza Zerehpoosh ,Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair ,Annals of Nuclear Energy ,vol. 0 ,2025 ,pp. 110902-0 ,

Conferences

M.R. Nematollahi،Mohammad Nazififard ,Heat Transfer Analysis of Nuclear Fuel Elements Displacement in Typical Fuel Assesmbly ,The Second International Conference on Nuclear and Renewable Energy Resources ,
M.R. Nematollahi،Mohammad Nazififard ,Thermo-Hydraulic Analuysis of a Typical Research Reactor Fuel Assembly By CFD methor ,The Second International Conference on Nuclear and Renewable Resources ,
Hamed Atajafari،M.R. Nematollahi ,Thermo-Hydraulic LOOP Modeling for SBWR Stabukuty Unvestugation Under Start -UP Cindition ,The Secons International Conference on Nuclear and Renewable Energy Resources ,
babak khonsha،M.R. Nematollahi،Mohammad Nazififard ,Comparison of Physical Properties effects on Mixing Jets Categorization in T- Junction Area with a Elbow Upstream for a ,the second international conference on nuclear and renewable energy resources ,
M.R. Nematollahi،موسی زارع ثانی ,thermal -hydraulic analysis of thermal fatigue with developing an optimum opreating condition ,14th international conferense on emerging systems ,
Kamal Hadad،Seyedmohammad Mirvakili،Saiedeh Safaei Arshi،M.R. Nematollahi ,reactivity induced accidenst analysis for a vver-1000 ,14th internatinal conference on emerging nuclear energy systeme ,
،Ebrahim Goshtasbi Rad،M.R. Nematollahi،Homayoun Emdad ,Coherent structure of the turbulent jet in a T-junction area with a 90-deg bend upstream ,17th Annual /International Conference on Mechanical Engineering ,
M.R. Nematollahi،Mohammad Hadi Akbari ,Vibration Mechanisams of A Heated Rod Due To Subcooled Boiling Flow ,ASME Pressure vessele 2006 ,
Mohammad Hadi Akbari،M.R. Nematollahi ,Comparison of Flow - Induced Vibrations Versis Subcooled Boiling - Induced Vibrations on a Heated Rod in Axial Flow ,ASME pressure vessels 2006 ,
Mohammad Hadi Akbari،M.R. Nematollahi ,COMPARISON OF FLOW-INDUCED VIBRATIONS VERSUS SUBCOOLED BOILING-INDUCED VIBRATIONS ON A HEATED ROD IN AXIAL FLOW ,Proceedings of PVP2006-ICPVT-112006ASME Pressure Vessels and Piping Division Conference ,
M.R. Nematollahi،M. Hashemi Tilnouei ,Nuclear Reactor Control Rod Drive Mechanism with Linear DC Motor ,کنفرانس هسته ای ایران ,
M.R. Nematollahi،Mohammad Hadi Akbari ,VIBRATION MECHANISMS OF A HEATED ROD DUE TO SUBCOOLED BOILING FLOW ,proceedings of PVP2006-ICPVT -11 2006 ASME PRessure Vessels and Piping Division ,
Kamal Hadad،M.R. Nematollahi ,Fault Detection of VVER-1000 NPP Using MLP Neural Network and Dynamic Sequential Windows ,کنفرانس هسته ای یزد ,
M.R. Nematollahi،Kamal Hadad،Abdoljavad Jaafarpour ,Typical Steam Generator Tube Rupture Effect on Thermohydralics parameters of VVER-1000 Primary Loop ,13th int .Conf.emerging nuclear energy systems ,
Mohammad Nazififard،M.R. Nematollahi ,Enhancement of Heat Transfer in a Typical Pressurized Water Reactor by Different Mixing Vanes on Spacer Grids ,International Cinference on Engineering Nuclear Energy System ,
M.R. Nematollahi،Kamal Hadad ,Typical Steam Generator Tube Rupture (SGTR) Effection on Termohydraulic Parameterso of VVR-1000 Primary Loop ,International Conference on Engineering Nuclear Energy System ,
،M.R. Nematollahi ,Determination of Shielding Parameters for different Types of Concreters by Monte Carlo Methods ,International Cinference on Engineering Nuclear Energy System ,
M. Hashemi Tilnouei، ،M.R. Nematollahi ,Fossil and Nuclear Power Plant Pollution & their effects on our enviroment ,همایش جایگاه سوخت هسته ای در توسعه فن آوری و تحقیقات ,
M.R. Nematollahi،Kamal Hadad ,بررسی فرسایش سوخت و حفاظ های موجود در استخر نگهداری سوخت نیروگاه بوشهر ,کنفرانس هسته ای ایران ,
موسی زارع ثانی،M.R. Nematollahi ,CFD examination of thermal mixing in a T- joiction area ,Fourth International Conference on Thermal Engineering ,
،M.R. Nematollahi ,CFD Analysis of Turbulent Heat Trasfer in a Hexagonally Arranged Fuel Assemb;y ,Fourth International Conference on Thermal Engineering ,
Mohammad Nazififard،M.R. Nematollahi،Seyedmohammad Mirvakili ,Flow Simulation of BODY- CENTERD Cubic Pcked Pebble Bed Modular Reactor Core Using Computational Fluid Dunamic ,Fourth International Conference on Thermal Engineering ,
M.R. Nematollahi،Mohammad Nazififard ,Heat Transfer Analysis of Displacement Nuclear Fuel Elements in a Typical Fuel Assembly ,Fourth International Conference on Thermal Engineering ,
M.R. Nematollahi، ،Mohammad Nazififard، ، ,Effect of Bend Curvature Ratio on Flow Pattern at a Mixing Tee after a 90 Degree Bend ,Fourth International Conference on Thermal Engineering ,
M.R. Nematollahi،Mohammad Nazififard ,Fire Risk Evaluation for NPPs ,اولین سمینار بین المللی تبادل تجربیات طراحی و ساخت نیروگاههای هسته ای ,
M.R. Nematollahi،Mohammad Nazififard ,Evaluation of Heat Transfer Shear of Different Mechanisms in Subcooled Nucleat e Boiling ,Fourth International Conference on Thermal Engineering ,
M.R. Nematollahi ,Evaluation of Exerting Force on the Heating Surface Due to Bubble Ebullition in Subcooled Flow Boiling ,proceedings of world academy of science engineeting and techonology ,
Seyedmohammad Mirvakili، ،M.R. Nematollahi،Mohammad Nazififard ,Thermal -hydraulic trasient analysis for a typical PWR with COBRA - EN code ,proceedings of the Fourth international Conference on Thermal Engineering Theory and Applications ,
Kamal Hadad،M.R. Nematollahi،Navid Ayoobian ,Efect of steam line breaks on increasing the secondary -side heat removal in a VVER-1000 reactor type ,proceedings of the Fourth international Conference on Thermal Engineering Theory and Applications ,
،M.R. Nematollahi ,evaluation the consequences of loss of flow acident for a typical nuclear power plant ,پانزدهمین کنفرانس هسته ای کشور ,
M.R. Nematollahi ,evaluation of exerting force on the heating surface due to bubble ebulition in subcooled flw boiling ,Fourth International Conference on Thermal Engineering ,
M.R. Nematollahi ,the secondary- side heal removal in a vver reactor type 1000 /?????????????????????????????????????? ,nununu ,
M.R. Nematollahi، ,Non-Uniform Two- phase Flow Analysis in Gas Cooled Reactor Steam Generator Pipes with ,Congress on Peaceful Application of Nuclear Technology ,
amir ramezanzadeh moghadam،M.R. Nematollahi ,Online Prediction oif Boiling Regime by Sound Analysis in Subcooled Pool Boiling ,Congress on Peaceful Application of Nuclear Technology ,
M.R. Nematollahi، ,Using Risk Assessment Tool to Evaluate the Fire induced Core Damage Freqyency ,Congress on Peaceful Application of Nuclear Technology ,
Reza Faghihi،M.R. Nematollahi ,Variation of indoor radon concentration in iran with internal wall covering materials ,Congress on Peaceful Application of Nuclear Technology ,
Kamal Hadad،M.R. Nematollahi،milad baradaran ghahfarrokhi،mohammad reza hakimdavuod ,Steady State and Long Term Relation of Temperature Relative Humidity Air Flow Ventilation Rate with ,14 th International Conference on Emerging Nuclear Energy Systems ,
،M.R. Nematollahi ,Evaluating the reliability of AP1000 passive core cooling systems with risk assessment ,IMECS 2010 ,
M.R. Nematollahi، ,Evaluating the core damage ferequency of a TRIGA research reactor using risk assessment tool software ,IMECS2010 ,
،M.R. Nematollahi،Mahmoud Famouri ,Using Risk Assessment Tool to Evaluate the Fire-Induced Core Damage Frequency ,World Congress on Engineering 2010 ,
M.R. Nematollahi،mahdi rezaiean ,Failure Analysis of Low Pressure Evaporator Tubes in a Typical Combined ,2011 International Conference on Mechanical and Aerospace Engineering ,
shahab addin kamyab،M.R. Nematollahi ,Criticality Analysis of the Fuel Fabrication Facility ,INTERNATIONAL SYMPOSIUM ON FUTUR FOR NUCLEAR POWER PLANTS........... ,
zahra mokhtari homami،M.R. Nematollahi،shahab addin kamyab ,Criticality safety Evaluation for 30B and 48X UF6 cylinders ,ICI2011 ,
M.R. Nematollahi،Mohamadreza Mazhari ,QUANTITATIVE EVALUATION OF HEAT TRANSFER IN BUBBLE COLLAPSE PROCESS IN SUBCOOLED ,15th International Conference on Emerging Nuclear Energy Systems (ICENES2011) ,
M.R. Nematollahi،Mohammad Nazififard ,Heat Transfer Analysis of a Mixing Vane on the Hexagonally Arranged ,15th International Conference on Emerging Nuclear Energy Systems (ICENES2011) ,
M.R. Nematollahi،mahdi rezaiean ,EXPERIMENTAL EVALUATION OF NATURAL CIRCULATION PRESSURE DROP IN A BOILING CHANNEL ,15th International Conference on Emerging Nuclear Energy Systems (ICENES2011) ,
Mohammad Nazififard،M.R. Nematollahi،Kune Y. Suh ,NUMERICAL ANALYSIS OF WATER-BASED NANOFLUID COOLANT FOR SMALL MODULAR REACTOR ,ASME 2011 Small Modular Reactors Symposium ,
kobra fatehimarj،Kamal Hadad،M.R. Nematollahi،Mohamad mahdi khalife shoshtari ,Analysis of natural circulation in station blackout accident at Bushehr VVER-1000 Nuclear Power Plant ,NuRER 2012 – III. International Conference on Nuclear & Renewable Energy Resources ,
golnoush shafiee،shahab addin kamyab،M.R. Nematollahi،Kamal Hadad، ,SUCCESS CRITERIA ANALYSIS FOR A REACTOR TRIP SYSTEM UPON LOSS OF OFFSITE POWER IN THE TYPICAL WWER 1000 ,NURER 2012 ,
Mohammad Nazififard،M.R. Nematollahi،Kune Y. Kun Suh ,Turbulent Enhanced Mixing Analysis (TEMA) in a Hexagonally Arranged Fuel Bundle of a Typical Heavy Water Nuclear Reactor ,9th International Conference of Numerical Analysis and Applied Mathematics ,
Mohammad Nazififard،M.R. Nematollahi،Kune Y. Suh ,CFD Study of In-Core Partial Flow Blockage by Insulation Debris for a Typical Water Cooled Small Modular Reactor ,Transactions of the Korean Nuclear Society Autumn Meeting ,
Mohammad Nazififard،M.R. Nematollahi،Kune Y. Suh ,Computational Fluid Dynamic Analysis of Alumina Nanofluid Coolant for a typical PWRs , Korean Nuclear Society Spring Meeting ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y. Suh ,Computational Fluid Dynamics in ThO2 Pressurized Water Reactor Fuel ,Thermal and Fluids Engineering 2012 ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y. Suh ,ANALYSIS OF COOLANT MIXING IN THE VVER-1000 FUEL ASSEMBLY ,The 18th Pacific Basin Nuclear Conference (PBNC 2012) ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،K.Y. Suh ,Detailed CFD Analysis of Convective Heat Transfer of Alumina Nanofluid in Subchannel ,ICFD 2012 ,
Mohammad Nazififard،M.R. Nematollahi،K. Y. Suh ,Thermohydrodynamic Analysis of Water Based Al2O3 Nanofluid forFusion Reactor Engineering ,The Fifth China-Korea Workshop on Nuclear Reactor Thermal Hydraulics ,
Mohammad Nazififard،M.R. Nematollahi،Khosrow Jafarpur،Kune Y. Suh ,Computational Fluid Dynamics Assisted Performance Evaluation of Commercial Split Vane Grid Spacer in a System-Integrated Modular Reactor ,The 9th International Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) ,
shahab addin kamyab،golnoush shafiee،M.R. Nematollahi ,Reevaluating the Effectiveness of SBO Coping Features in a Typical Advance Pressurized Water Reactor ,NURER 2012 ,
Mohammad Nazififard،Kune Suh،M.R. Nematollahi ,Augmented Heat Transport of Mono-Sized Sphere-Packed Pipe for Force Free Helical Reactor ,Transactions Korean Nuclear Society Autumn Meeting ,
Mohammad Nazififard،M.R. Nematollahi،kune suh ,FLUENT Simulation of Nanofluid in Subchannel of a Typical PWR ,Transactions American Nuclear Society Winter Meeting ,
Ahmad Pirouzmand،peyman dehghani،Kamal Hadad،M.R. Nematollahi،Ebrahim Sharifi ,ASSESSMENT OF RADIONUCLIDE DISPERSION FROM BUSHEHR NUCLEAR POWER PLANT DURING NORMAL AND ACCIDENT CONDITIONS ,The 4th international conference on nuclear and renewable energy resources ,
Kamal Hadad،peyman dehghani،M.R. Nematollahi ,Atmospheric dispersion modeling for an accidental release from the Bushehr Nuclear Power Plant using HYSPLIT ,NURER 2014 ,
Kamal Hadad،M.R. Nematollahi، ,GENERATING THE CROSS SECTION LIBRARY FOR VVER-1000 REACTOR BASED ON JENDL IV BY MCNPX ,NURER2014 ,
Kamal Hadad، ،M.R. Nematollahi ,RADIATION ANALYSIS OF THE SPENT FUEL POOL OF THE BUSHEHR NUCLEAR POWER PLANT IN THE TIME OF AN INCIDENT ,NURER2014 ,
M.R. Nematollahi، ،behnam behzadi nejad ,FEASIBILITY STUDY OF USING NANO-FLUIDS AS A NEUTRON ABSORBER IN REACTOR EMERGENCY CORE COOLING SYSTEM ,International Conference on Nuclear and Renewable Energy Resources ,
M.R. Nematollahi، ،behnam behzadi nejad , FEASIBILITY STUDY OF USING NANO-FLUIDS AS A NEUTRON ABSORBER IN REACTOR EMERGENCY CORE COOLING SYSTEM ,International Conference on Nuclear and Renewable Energy Resources ,
M.R. Nematollahi،Ali Erfaninia ,NUMERICAL STUDY OF FLOW ACCELERATED CRROSION IN A T-JUNCTION USING COMPUTAIONAL FLUID DYNAMICS ,International Conference on Nuclear and Renewable Energy Resources ,
Mohammad Nazififard،M.R. Nematollahi،Kune Y. Suh ,ANALYSIS OF TURBULENT HEAT TRANSFER ENHANCEMENT IN VVER-1000 FUEL ROD BUNDLE ,International Conference on Nuclear and Renewable Energy Resources ,
M.R. Nematollahi،Mohammadhadi Porhemmat،Khalil Hosseini Pour Noghani ,MODELING OF FORCE ACTING ON A HEATED ROD SURFACE IN SUBCOOLED FLOW BOILING CONDITION ,International Conference on Nuclear and Renewable Energy Resources ,
M.R. Nematollahi،Ali Erfaninia،samira salatini , REDUCTION OF CORE DAMAGE FREQUENCY VIA NEW DESIGN FOR EMERGENCY CORE COOLING SYSTEM IN A TYPICAL PWR ,International Conference on Nuclear and Renewable Energy Resources ,
Somayeh Bagheri،behnam behzadi nejad،M.R. Nematollahi،Farshad Faghihi ,Assessment of Thermal Hydraulic Parameters of VVER-1000 During Transient Conditionsof Reactivity Insertion ,ICENC2015 ,
Somayeh Bagheri،behnam behzadi nejad،M.R. Nematollahi،Farshad Faghihi ,Thermal-hydraulic Behavior of a Typical VVER-1000 Core at different void model ,ICENC2015 ,
M.R. Nematollahi،Kamal Hadad،Masoud Jabary،zahra tabadar،gh Ansarifar ,Calculation of maximum pressure on containment surface in accident LOCA by using numerical calculation and experimental method in reactor VVER-1000 ,ICENES2015 ,
Kamal Hadad،M.R. Nematollahi،zahra tabadar،GH Ansarifar،Masoud Jabary ,Calculation of Control Rod Group’s Worth Calculation of VVER-1000 Reactor Core by MCNPX Code and comparison with Experimental Data ,ICENES2015 ,
Kamal Hadad،M.R. Nematollahi،Hoda Sadeghpour،behnam behzadi nejad ,Moderation and Shielding optimization for a 252Cf based Prompt Gamma Neutron Activation Analyzer system ,ICENES2015 ,
Mahmood Yaghoubi،Sajad Bashiry،M.R. Nematollahi، ,Experimental study of surface configuration effect on saturated pool boiling ,Turbulence Heat and Mass Transfer 8 ,
behnam behzadi nejad،Somayeh Bagheri،M.R. Nematollahi،Farshad Faghihi ,Assessment of Thermal Hydraulic Parameters of VVER-1000 During Transient Conditions Reactivity Insertion ,ICENES2015 ,
M.R. Nematollahi، ،Masoud Ahmadi، ,Multi element neutron activation analysis precision with K0-NAA compared to INAA method in Esfahan MNSR research reactor ,International Conference on Emerging Nuclear Energy Systems (ICENES2015) ,
M.R. Nematollahi،Masoud Ahmadi، ، ,Calculation and measurement of neutron flux distribution in the Isfahan Miniature Neutron Source Reactor ,International Conference on Emerging Nuclear Energy Systems (ICENES2015) ,
Ali Erfaninia،M.R. Nematollahi , NUMERICAL STUDY OF MASS TRANSFER COEFFICIENT IN A T-JUNCTION ,International Conference on Emerging Nuclear Energy Systems (ICENES2015) ,
M.R. Nematollahi،Ali Erfaninia،mohammadhossein mirzamohammadzadeh ,AN INNOVATIVE PASSIVE HEAT REMOVAL SYSTEM FOR A TYPICAL VVER REACTOR IN THE CASE OF STATION BLACKOUT ACCIDENT ,International Conference on Emerging Nuclear Energy Systems (ICENES2015) ,
M.R. Nematollahi،Abbas Sedghkerdar ,GAMMA-RAY DOSE BUILDUP FACTOR CALCULATION FOR SERPENTINE AND STAINLESS STEEL CONCRETE DOUBLE-LAYERED SHIELDS ,The International Conference on Emerging Nuclear Energy Systems (ICENES2015) which takes place in Istanbul Turkey during 04-08 October 2015. ,
M.R. Nematollahi،Negin Afshar ,FLUKA and MCNP in Oil Exploitation and Earth Structure Simulation ,The International Conference on Emerging Nuclear Energy Systems (ICENES2015) which takes place in Istanbul Turkey during 04-08 October 2015. ,
M.R. Nematollahi،Negin Afshar ,Assessment of Using Muon Radiography in Fuel Depletion of Tehran Research Reactor ,The International Conference on Emerging Nuclear Energy Systems (ICENES2015) which takes place in Istanbul Turkey during 04-08 October 2015. ,
M.R. Nematollahi،Negin Afshar ,Analysis Core Life-Time and Optimum Fuel Loading of Tehran Research Reactor HEU Fuel in a Fresh LEU research reactor by studying on actinide and fission product inventory with WIMS and CITATION ,The International Conference on Emerging Nuclear Energy Systems (ICENES2015) which takes place in Istanbul Turkey during 04-08 October 2015. ,
M.R. Nematollahi،Shahabeddin Kamyab ,Sensitivity Analysis for F-SLOCA Induced CDF Variation on the Conditional Probability of Spurious Operation of Pressurizer SDVs due to Fire Induced Hot Short ,The International Conference on Emerging Nuclear Energy Systems (ICENES2015) which takes place in Istanbul Turkey during 04-08 October 2015. ,
M.R. Nematollahi،Mohammad Aghaee Foroushani،Mojtaba Binazadeh ,Feasibility study of floating solar cell technology for electricity generation for Agriculture Purposes and simultaneous Elimination of Water Evaporation from Dams and Water Storage Pools ,ششمین همایش ملی آب، پساب و پسماند ,
Shahabeddin Kamyab،M.R. Nematollahi ,Sensitivity Analysis on the Effect of Configuration of Offsite Power Supply to a PWR Nuclear Power Plant on Full Power Core Damage Frequency ,The 4th International Reliability Engineering Conference IREC2016 ,
Mohsen Ebrahimian shams abad،M.R. Nematollahi ,Probabilistic Safety Analysis of a Feed water Piping Failure in a PWR due to FAC ,The 4th International Reliability Engineering Conference IREC2016 ,
Meysam Rafiei،M.R. Nematollahi،Shahabeddin Kamyab،Mohsen Ebrahimian shams abad ,Determination of Vulnerable areas to Flow-Accelerated Corrosion Utilizing Risk Based Inspection Concepts ,The 4th International Reliability Engineering Conference IREC2016 ,
Behzad Salmassian، Seyedmohammad mirvakili،M.R. Nematollahi،Bahareh Sabetan ,Modeling and analysis of Tehran research reactor against loss of flow accident ,The 4th International Reliability Engineering Conference IREC2016 ,
Kamal Hadad،Seyed fazel Ghazi ardekani،M.R. Nematollahi ,Evaluation of Radiation Damage in BNPP Reactor Pressure Vessel ,ICENES2017 ,
Kamal Hadad،Ali Moghaddam،M.R. Nematollahi،Mohammadhadi Porhemmat ,TRANSP Deterministic Photon Transport with the Method of Characteristic ,AAPM2017 ,
M.R. Nematollahi،Mohsen Ebrahimian shams abad،Farhad Salari،Maryam Mohammadi ,Sensitivity Analysis of the Cladding Materials on the Neutronic and Thermohydraulic Parameters of VVER-1000 Nuclear Reactor ,ICENES 2017 ,
Ali Erfaninia،M.R. Nematollahi ,The Study of the Hydrodynamic Parameters Effects on the Flow Accelerated Corrosion in a 90-degree Straight T-junction by Using CFX and 2D PIV ,ICENES2017 ,
M.R. Nematollahi،Ali Erfaninia، ,The Study of the effect of Spacer and Entrance Coil on the Turbulent Heat Transfer in a Hexagonal Fuel Assembly in a Typical Research Reactor ,ICENES 2017 ,
Shahabeddin Kamyab،M.R. Nematollahi،Kamal Hadad ,Using MCNP for Success Criteria Evaluation of Reactor Trip Function in Probabilistic Modelling of ATWS upon LOOP ,ICENES 2017 ,
M.R. Nematollahi،Sahar Ghaseminejad ,Evaluation of Control rods worth and Shutdown Margin at Various Normal Operation of the VVER-1000 Reactor ,ICENES 2017 ,
M.R. Nematollahi،Shahabeddin Kamyab ,Comparative Analysis of Large Event Tree-Small Fault Tree Model Versus Small Event Tree-Large Fault Tree for a Case Study on Reactor Trip in a Typical WWER-1000 NPP ,ICENES 2017 ,
Aliakbar Bahrami Dehtuti،Kamal Hadad،M.R. Nematollahi،Soheila MirCholi ,نرمافزار مدیریت برنامه های نگهداری و تعمیرات پیشگیرانه نرم افزار PMPM ,5th International Reliability and Safety Engineering Conference ,
Aliakbar Bahrami Dehtuti،M.R. Nematollahi ,Preventive Maintenance Programs Management Software PMPM Software ,5th International Reliability and Safety Engineering conference ,
،M.R. Nematollahi، ، ,Presenting preventive conservation project for Persepolis Museum ,5th International Reliability and Safety Engineering conference ,
Shahabeddin Kamyab،M.R. Nematollahi،Faramarz Yosefpour،Kaveh Karimi ,Analysis of Possible Exemption for Passive-Designed-Profited NPPs from GDC 17 of 10CFR50 ,5th International Reliability and Safety Engineering conference ,
M.R. Nematollahi،Fatemeh Roosta ,A typical safety research center for developing countries ,5th International Reliability and Safety Engineering conference ,
saied soltanmohammadi، ،M.R. Nematollahi ,Analysis of Fuel Rod Thermo-Mechanical Behavior and Its Fission Gas Release in Bushehr’s Spent Fuel Pool by Using of Frapcon-3 ,5th International Reliability and Safety Engineering conference ,
Shahabeddin Kamyab،Ahmad Pirouzmand،Faramarz Yousefpour،Kaveh Karimi،M.R. Nematollahi ,On The Use of Risk Surrogate in Maintenance Planning- A Case Study on the EDG of A Nuclear Power Plant ,The 6th International Conference on Nuclear and Renewable Energy Resources (NURER2018) ,
Siyamak Parsaei،M.R. Nematollahi،Kamal Hadad،Shahabeddin Kamyab ,The use of Multi-State Physics Modeling to Update Core Damage Frequency Induced by Steam Generator Tubes Rupture due to Aging ,NURER 2018 ,
Mohsen Ebrahimian shams abad،M.R. Nematollahi،Farhad Salari ,The effect of using different materials of fuel cladding on the neutronic and thermal-hydraulic parameters of the VVER-1000 Reactor ,5th International Conference on Power Generation Systems and Renewable Energy Technologies ,
babak khonsha، ، ،M.R. Nematollahi ,Validation of Scaling and Thermal-Hydraulic Design of a Test Loop for VVER-1000 Reactor ,TRADITIONAL INTERNATIONAL NUCLEAR CONFERENCE BULGARIAN NUCLEAR ENERGY – NATIONAL REGIONAL AND WORLD ENERGY SECURITY ,
babak khonsha، ،M.R. Nematollahi، ,Thermal-Hydraulic Investigation of Single-Phase Natural Circulation Flow in a Test Loop Core ,TRADITIONAL INTERNATIONAL NUCLEAR CONFERENCE BULGARIAN NUCLEAR ENERGY – NATIONAL REGIONAL AND WORLD ENERGY SECURITY ,
Kamal Hadad،Shirin Mokhtari،M.R. Nematollahi ,GUI Development for SMART Deterministic Code for Homo-And-Heterogeneous Voxel Phantoms and Evaluation of the Results ,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 ,
Arefoddin Zarnousheh Farahani،Faramarz Yosefpour،Ahmad Pirouzmand،M.R. Nematollahi ,Fission Product Behavior during Ex-Vessel Phase of the LB-LOCA Severe Accident in PWR ,ICNST22 ,
Ahmad Pirouzmand،Arefoddin Zarnousheh Farahani،M.R. Nematollahi ,Deterministic analysis of emergency water injection strategy during SBO ,ICNST22 ,
Masoud Jabary،Kamal Hadad،M.R. Nematollahi،Ahmad Pirouzmand،zahra tabadar، ,ارتقائ سیستم های ایمنی واحدهای جدید در مقایسه با واحد یکم نیروگاه اتمی بوشهر جهت مقابله با حادثه بی برقی ,دومین همایش ملی پژوهشهای نوین در نیروگاههای هسته ای ,
Hossein Mohammadi ،M.R. Nematollahi،Ahmad Pirouzmand ,Determining the Location of Hydrogen Recombiners in the Containment of VVER-1000/V446 Nuclear Reactor ,ICNST22 ,
،M.R. Nematollahi ,Simulation and analysis of fire accident in Isfahan nuclear fuel production complex and standardization of fire extinguishing system according to NFPA global standard using CFAST code ,ICNST2024 ,
Arefoddin Zarnousheh Farahani،M.R. Nematollahi،Ahmad Pirouzmand , Modeling Comparison and Analyses of Fire Protection System Using Three Probabilistic Safety Analysis Code ,ICNST2024 ,
Kamal Hadad،M.R. Nematollahi ,Analysis and Construction of Serpentine-Galena Mixed Concrete as a Replacement of Barium Sulfate Concrete for the Shielding of beam facility ,First International Conference on the Exchange of Scientific Information in the Fields of Concrete Structures and Materials (ICConcrete) ,

Fundamentals

FirstName And Last Name	Project Name	Degree	def-date

	BEHAVIOUR OF BUBBLE IN NUCLEAT BOILING	M.S	1381/04/01
	Analysis of BNPP Spent Fuel Pool Shielding Using WIMS4-D & MCNP4C Codes and Comparison with PSAR Data	M.S	1384/05/05
	Measuring the concentration of heavy metals in the soil of farms around Shiraz refinery using neutron activation analysis method (NAA)	M.S	1400/06/31
	Simulation of Research Loop LOBI-MOD2 with RELAP5 Code for Thermo hydraulic Accident Analysis in Nuclear Power plant	M.S	1384/12/23
	Probabilistic Safety Assessment of Tehran Research	M.S	1382/06/26
	ارزیابی احتمالاتی ایمنی(PSA) راکتور تحقیقاتی تهران	M.S	1382/06/26
	BOILING DETECTION ON THE BASIS NEUTRON NOISE ANALYSIS BY NEURAL NETWORK	M.S	1380/11/01
	Analysis Of Conjugate Conduction-Convection Heat Transfer In Nuclear Reactor Fuel Assembl	M.S	1382/11/26
	Heat transfer from nuclear reactor fuel rods due to swirl flow	M.S	1383/04/14
	Typical Steam Generator Tube Ruptures (SGTR) Effect On Thermo-Hydraulic Parameters of VVER-1000 Primary Loop	M.S	1385/12/26
	Design and Implementation of a Risk Monitor and its Application for a Typical Research Reactor	M.S	1385/02/27
	Simulation of beam hardening artifact in CT scan with X-ray and radioisotope sources and Feasibility study for manufacturing of industrial CT scan with radioisotope	M.S	1386/06/20
Mahtab Adine	Quantitative Evaluation of Void Fraction in Two Phase Flow inside Vertical Tubes by Gamma-Ray	M.S	1391/05/24
mohammadesmaeel amirsoltani	Development of Dynamic Event Tree to Calculate the Core Damage Frequency (CDF) in SBO Accident for VVER-1000/V446 Reactor	Ph.D	1400/11/03
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
sajad bashiry	Experimental Measurement of heat transfer coefficient in nucleate boiling for surfaces with different roughness	M.S	1390/06/30
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
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
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
mohamad ali dast belaraki	Redesign of Nuscale reactor core with fresh fuel and dynamic performance calculations and burnup in the first and second cycle	M.S	1399/06/30
peyman dehghani	Assessment and Comparison of Radionuclide Dispersion from Bushehr Nuclear Power Plant Stack During Normal and LBLOCA Condition and Its Effect on Population Using : CAP88, HYSPLIT, HOTSPOT and RASCAL Codes	M.S	1393/06/31
mohsen dehghan	Numerical Study of Flow Field Downstream of Typical Orifice in Power Plants by CFD Method	M.S
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
Ali Erfaninia	NUMERICAL AND EXPERIMENTAL ANALYSIS OF HYDRODYNAMIC PARAMETERS EFFEC ON FLOW ACCELERATED CORROSION AT THE T-JUNCTION	Ph.D	1396/02/13
maryam farajpour	Dynamic Assessment of Core Damage Frequency by Fire Initiating Event in Tehran Research Reactor Building	Ph.D
kobra fatehimarj	Analysis of natural circulation in residual heat removal for a typical prissurized water reactor	M.S	1390/12/14
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
amin golestani	Analysis of the spent fuel storage pool for bushehr nuclear power plant (BNPP)	M.S	1392/07/09
sayyid nahid hadi	Investigation of Axial and Radial Power Peaking Factors in VVER-1000-V446 Core with TVS-2M Fuel Assemblies Using MCNPX Code	M.S	1396/12/20
nikoo jafari	Application of Gamma-Attenuation in Determination of Flow Density and Velocity in a Pipe using Monte-Carlo Simulation and Artificial Neural Network	M.S	1399/06/31
ABDOISAMAD JAFARI	Development of radon map and its correlation with residents’ health; Case study: Dwellings of South Fars	Ph.D
shahab addin kamyab	Risk monitoring software designing to evaluate AP1000 PCCS Reliability Improvement with due to Redundancy and CCFs	M.S	1389/06/01
Shahabeddin Kamyab	Development and Evaluation of Probabilistic-Deterministic Method for Estimation of Initiating Event Frequency of Grid Related Loss of Offsite Power to the Nuclear Power Plant	Ph.D	1399/10/29
MOHAMMAD JAVAD KHALEGHI	CFD Simulation of Onset of Nucleate Boiling on a Heated Rod With Sinusoidal Heat Generation	M.S
Mohammad Khalvandi	Analysis of Thermal Fatigue and FAC-Induced Effects in the Fluid Flow through the T-Junction of the Secondary Circuit Feed-Water Pipeline of BNPP	Ph.D
Niloufar Manouchehri charamakani	Assessment of Proposed Sites for the Establishment of Fars Research Reactor	M.S	1398/06/31
Mohamadreza Mazhari	Analysis of Bubble Behavior and Determination of Quantitative Portion of Heat Transfer Different Mechanisms of Subcooled Nucleate Boiling Region on a Heated Rod	M.S	1389/06/31
mohammad mehdi mirzaee	Simulation of SHUNCL Natural Circulation Loop Using RELAP5 code and Compare its Results with Experimental data	M.S	1393/11/19
Ali Moghaddam	Deterministic solution of photon transport equation by method of characteristic(MOC)in 2-D Cartesian geometry	M.S	1395/12/11
Yousef Mohseni	Analysis of Flow Accelerated Corrosion Downstream of Orifices in the Nuclear Power Plant Piping System	M.S	1400/06/31
Afsane Mojassami	Developing a computer code for fuel depletion calculations of first cycle of Boushehr reactor and its verfication with FSAR data	M.S	1396/06/28
zahra mokhtari homami	EVALUATION OF PRIMARY SAFETY PARAMETERS FOR A STORAGE FACILITY OF UF6 CYLINDERS	M.S	1389/06/31
Shirin Mokhtari	GUI Development for SMART Deterministic Code to Utilize Dicom Images for Patient Specific Voxel Dosimetry in Nuclear Medicine	M.S	1400/02/29
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
Seyed Hossein Mousavi Fard	Radiation damage simulation of VHTR reactor pressure vessel by LAMMPS molecular dynamics code	M.S	1397/11/30
elham narooi	The termohydrolic analysis of cooling ITER reactor's divertor by using swirl flow	M.S	1392/12/03
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
mohammad nazififard	NUMERICAL AND EXPERIMENTAL ANALYSIS OF TURBULENT CONVECTIVE HEAT TRANSFER WITHIN A TYPICAL PRESSURIZED WATER REACTOR WITH NANOFLUIDS	Ph.D	1391/12/02
Mohammad Nazififard	THE EFFECT OF FUEL ASSEMBLY SPACER GRIDS ON HEAT TRANSFER PARAMETERS IN A TYPICAL PWR CORE	M.S	1385/10/05
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	Optimization and Risk-Informed Assessment of Maintenance Schedule of VVER-1000/V446 NPP ECCS	Ph.D
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
Najib allah Poorian khoob	Analysis and construction of serpentine-galena mixed concrete as a replacement of barium sulfate concrete for the shield of tehran research reactor beam tube	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
hossein raktor	Determining the Location of Hydrogen Recombiners in the Containment of VVER-1000/V446 Nuclear Reactor by MELCOR Code	M.S	1400/11/15
mohamad rashidi toghroljerdi	Simulation of Sphere Packed Pipe (SPP) Using Computational Fluid Dynamics	M.S	1393/03/11
Majid Razeghianjahromi	Simulation and Evaluation of a Typical Nuclear Fuel Manufacturing Plant Safety Level in Fire Accidents	M.S	1390/04/19
mahdi rezaiean	Experimental Evaluation of Acceleration Pressure Drop and it’s Role on Natural Circulation Driving Pressure due to Water Boiling in a Circular Channel	M.S	1390/04/18
hoda sadeghpour	Monte Carlo Simulation and Experimental Measurement of Replacement Sources for PGNAA in Material Analysis in Cement Industry	M.S	1392/11/29
Saiedeh Safaei Arshi	Probabilistic safety assessment of fire at Tehran research reactor containment	M.S	1386/12/20
samira salatini	Probabilistic safety assessment of promoted emergency core cooling system (ECCS) of IR-360 nuclear power plant	M.S	1390/04/20
Behzad Salmassian	The VVER-1000/446 core blockage location diagnosis using neutron detectors and neural networks	Ph.D	1400/06/31
Ali Sattaripour	Investigating the effect of amorphous Fe-based nano-coatings on the prevention of radiation damage in VVER-1000/446 nuclear reactor pressure vessel	M.S	1399/06/31
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
golnoush shafiee	Analysis of control rods function following loss of offside power for evaluating the success of reactor trip system in a typical reactor	M.S	1390/12/10
Mohammad Shahsavani	Using Accumulator to Emergency Core Cooling of a Typical Research Reactor and Probabilistic Safety Analysis of it	M.S	1393/11/28
poria soroush	Turbulence flow simulation on AP-1400 fuel assembly by CFD method	M.S	1392/12/19
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
reza zhorevand khedry	Calculation of the Volume of Storage Water Required to Provide Cooling of the VVER-1000/V446 Reactor Core for the LOCA Accidents in Beyond Design Conditions	M.S	1400/11/15
موسی زارع ثانی	Numerical Simulation of Thermal Mixing of Two Water Streams with Different Temperatures in a T-Junction Downstream of a 90-Deg Elbow	M.S	1388/06/01
	Primarily Hazard Analysis for Fuel Fabrication Facility	M.S	1383/06/01
	SIMULATION OF THE EFFECT OF A SMALL-BREAK LOSS OF COOLANT ACCIDENT (SBLOCA) TRANSIENT ON VVER-1000 REACTOR PRESSURE VESSEL PARAMETERS	M.S	1385/06/22
	SAFETY MARGIN DETERMINATION OF SINTERING FURNACE OF UO2 PELLETS IN NORMAL OPERATION AND ACCIDENT CONDITIONS USING NJOY-97 & MCNP-4C CODES	M.S	1385/06/29
	Hazard and Safeguard Evaluation and Classification of Consequences	M.S	1383/06/19
	Procedures of Shutdown Probabilistic Risk Assessment for a Typical Pressurized Water Reactor	M.S	1384/04/28
	Probabilistic safety assessment level 1 (PSA 1) for primary coolant circuit of a typical HWRR	M.S	1385/06/21
	Optimization Of The Mechanical Parameters For Molecular Separation By Fast Coaxial Rotating Cylinders	M.S	1388/06/30
	Simulation of Power and reactivity control in a research reactor	M.S	1383/06/01
	Nuclear Fuel Depletion Analysis of Bushehr Nuclear Power Plant in its First Operational Period	M.S	1386/06/31
	CALCULATING THE RATE OF PRODUCTED PU-239 FROM A SUPPOSED NUCLEAR FUSION REACTOR	M.S	1385/04/31
somayeh abassi	Analysis of the accidents related to the decrease of heat removal in VVER-1000 secondary side using RELAP5 and PSAR data	M.S	1390/06/30
Rouhollah Abbaszadeh	Extracting neutron cross sections from ENDF library for ANISN code	M.S	1387/11/15
Masoud Amin Mozafari	Neutronics and Thermal Hydraulics Design of the Next Generation VVER-1000 Reactor Using an Innovative Annular Fuel	Ph.D	1392/04/04
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
Alireza Atf	Thermo-hydraulic Analysis of Dryout Phenomenon in a Boiling Channel with the Injection of Nano Particle Al2O3	M.S	1393/12/19
Abdollah Avara	Experimental investigation and simulation of free convection heat transfer and condensation from humid air on a horizontal cylinder with a hydrophobic nano-structured surface	Ph.D
Mastaneh Behtash	Reliability Analysis of VVER-1000 Reactor Active Emergency Core Cooling System (ECCS) Using Markov Model	M.S	1396/06/19
Alireza Bonyadi sefat	Analysis of the NuScale reactor in the control rod withdrawal accident at various states of operation	M.S	1398/06/30
muhammda mahdi dana	Coupling computational fluid dynamics simulation and CO2 corrosion model for corrosion rate prediction in wet natural gas flow	Ph.D	1399/12/17
Mohsen Ebrahimian shams abad	Time-Variant Reliability Assessment of Passive Heat Removal System (PHRS) in VVER	Ph.D	1399/10/24
armin ghasemi kahrizi	Analysis of Large Break Loss-of-Coolant Accident (LBLOCA) for VVER-1000 Reactor Without Emergency Core Cooling System by SCDAP/RELAP5 Code	M.S	1393/06/31
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
Seyed fazel Ghazi ardekani	Evaluation of radiation damage in beltline region of VVER-1000/446 nuclear reactor pressure vessel	Ph.D	1396/04/10
mohammad gol mohammadi	Heat transfer analysis in the Bushehr reactor fuel pins and assessment of the stress and strain during four operational cycles using FRAPCON code	M.S	1402/11/17
anahita hajizadeh	Evaluation of nanofluid application in light water reactor (LWR) nuclear reactor coolant	M.S	1387/10/09
Yaser Hamidi athar	Evaluation of the Selected Site for the Construction of Fars Research Reactor from the View point of Radioactive Material Dispersion During Normal Operation and Accident	M.S	1397/04/16
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
Mohammad Irvani	Basic design of a self-contained long life SMR reactor	M.S	1397/06/31
Masoud Jabary	Station black out accident scenario preparation for implementation of stress test program in Bushehr NPP	Ph.D	1398/06/31
masoud jabary	Detection of Break and Leak of Pipe Lines of Bushehr Reactor by Using Neural Networks	M.S	1389/06/31
fereshte joneirani	Cargoes Inspection for Nuclear Material Detection by Using Non-Destructive Photo-Neutrons Technique	M.S	1390/12/15
mohammad mansourimanesh	Numerical investigation of the stress field created in the pressurizer of Bushehr nuclear power plant unit-1 due to the emergency shutdown	M.S	1402/11/15
navid mehdizade afrozi	A simulation tool developments via coupling of neutronics and thermal-hydraulics calculations for a typical research reactor	M.S	1390/07/06
Mahshad Meshksar	Research and development center of renewable energy	M.S	1389/12/01
Seyedmohammad Mirvakili	Neutronic analysis of the Isfahan miniature research reactor and its burn up calculations using WIMS-D4 and CITATION codes	M.S	1386/06/24
mohammadhossein mirzamohammadzadeh	Development of SOEP procedures for VVER-1000/446 nuclear reactor in SBLOCA accident using RELAP5 code	Ph.D	1401/06/29
Fatemeh Mohammadhasani	Risk-Cost Based Maintenance Strategy Determination with Considering Aging Effect for Critical Components of Safety Systems in VVER-1000/V446 Nuclear Power Plant	Ph.D	1400/03/19
Hamidreza Mohammadi	Experimental study of pool boiling parameters using plasma coating on a hot surface	M.S	1399/06/23
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
zahra nasimi	Investigation of fluid-structural interaction of fuel rods using one-way coupling approach	M.S	1401/06/31
mohamad hoda nasirizade	Fabrication and study of titanium oxide nanotube electrodes for Dye-Sensitized Solar Cells(DSSC)	M.S	1391/12/14
mohamad reza nasirizade	Fabrication and evaluation of titanium dioxide nanotube arrays by anodization	M.S	1391/12/14
A. Piroozmand	Solution of One and Two Dimensional Time Dependent Neutron Transport Equation in Cartesian Geometry Using Cellular Neural Network (CNN)	Ph.D	1390/02/01
mohammad hadi porhemmat	Investigation of Transient States in VVER-1000 Bushehr Reactor Using PARCS Code	M.S	1392/06/30
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
seyedeh saeideh saadat	Quantitative Accuracy Evaluation of RELAP5 Accident Applied to LOBI Experimental Test Facility Data	M.S	1389/12/01
Majid Saadatpour	A PWR Power Plant Primary Loop Modeling With Fuzzy - Wavelet Networks and Monitoring on It’s Component Operation After a Typical Accident Occurrence	M.S	1390/03/31
seyedamir saeidi sini	Development of a radiochemical dosimeter for use in dosimetry of X, and gamma ray fields	M.S	1401/11/15
farhad salari	Assessment of the core corium catcher safety system for typical VVER-1000 nuclear reactor during severe accidents	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
mahdi sharifi	USING EMPIRICAL EIGENFUNCTIONS OBTAINED FROM POD ANALYSIS OF EXPERIMENTAL DATA TO SOLVE TWO-DIMENSIONAL INCOMPRESSIBLE NAVIER-STOKES EQUATIONS	M.S	1388/06/31
saied soltanmohammadi	Assessment of VVER-1000/V446 nuclear power plant containment integrity against the hydrogen explosion risk under sever accidents	Ph.D
amir hossein vosooghi	Investigation Of Flow Parameters On The Performance Of A Centrifugal Moisture Separator	M.S	1391/06/29
maryam_alsadat yousefniaye jahromi	Evaluation of Power Peaking Factor in a PWR due to Burn up Transients	M.S	1389/04/09
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
پریسا امیدی فرد	Analysis of Severe Accident Sequences in the Spent Fuel Pool of the VVER-1000/V446 Nuclear Reactor	M.S	1397/06/27
حیدر حیدری داد	Single Phase Natural Circulation Study of a Rectangular Loop Using Numerical Techniques and RELAP5/MOD3 Code	M.S	1386/06/28
پوریا قناعتیان جبذری	Uncertainty Analysis of Common Cause Failure Model Parameters and Assessment of their effects on CDF in LOCA Accidents	M.S	1397/11/21

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