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M.R. Nematollahi

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M.R. Nematollahi    (FA Page)

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Fundamentals




FirstName And Last Name Project Name Degree download-thesis 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
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 in the Bushehr annular fuel pin based on the finite element method and assessment of the stresses during four operational cycles 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 the emergency shutdown M.S 1402/12/05
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