Faculty Members

Farshad Faghihi

Farshad Faghihi

Farshad Faghihi    (FA Page)

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Books



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Fundamentals




FirstName And Last Name Project Name Degree download-thesis def-date
shielding desing for a neutronic source at nuclear engineering department using mcnp code M.S 1390/07/05
Determination Of Pu-Be Neutron Flux Using Activation Analysis And Its Symulation By MCNP-4B Code M.S 1384/06/01
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
Synthesis of the imprinted polymer for lead’s ion separation from nuclear waste and its performance investigation for removing the other environmental pollutants M.S 1390/07/20
A Survey Performance of Health Physic Protocols in CT Scan and Determination of Excess Critical Organ Dose, Due to non Observance of This Protocols in Different Hospitals of Fars Province M.S 1386/06/31
Analysis of Reactivity Effects and Reactivity Coefficients for VVER-1000 at Nominal Conditions M.S 1384/06/05
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
Masoud Abbasi VVER-1000 Managment Optimization Using Artificial Neural Network M.S 1392/12/20
elham abbasloo STUDY OF GEOMETRY, MATERIAL AND ARRANGEMENT OF THE BURNABLE POISON ON THE REACTOR PARAMETERS SUCH AS BURNUP AND POWER PEAKING FACTOR IN A VVER-1000 REACTOR M.S 1392/11/12
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
Rouhollah Abbaszadeh Extracting neutron cross sections from ENDF library for ANISN code M.S 1387/11/15
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
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
Sajjad Bahar Estimation of Corrosion in Insulated Pipes with Using Simulation of Gamma Ray Back Scattering Method M.S 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
Alireza Bonyadi sefat Analysis of the NuScale reactor in the control rod withdrawal accident at various states of operation M.S 1398/06/30
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
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
marjan dovalkhani study on the geometrical and enrichment variation of the tehran research reactor in the new proposef fuel assemblies M.S 1392/12/20
Ali Erfani nia Determine two safety coefficients of VVER-1000 reactor core including hexagonal annular fuel assemblies M.S 1390/11/03
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
Fatemeh Fereydoonpour Dosimetry calculations of the NuScale containment-pool and the received dose to the control room’s personnel, in the SBO accident condition M.S 1402/06/21
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
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
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
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
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
majid hasanzadeh Mathematical Modeling, Simulation and Analytical Studies on the UF4 Unit in a Screw Furnace (101B2) of the UCF Facilities Considering Nuclear Criteria M.S 1388/12/15
mahdi hassanzadeh Indoor radon concentration measurement and effective dose assessment of dwellings of old quarters in Mashhad city M.S
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
Khalil Hosseini Pour Noghani Analysis of Subgroup Self –Shielding Method and its Implementation Using an Accelerated MOC Solver. Ph.D 1398/06/30
fateme jafari Detection and measurement of Xenon_Iodine as well as neutron dose of the water around the Nuscale containment at the normal operation M.S 1402/12/16
ahmad kamgari Computational dosimetry of the head phantom based on Boron Neutron Capture Therapy using the Isfahan miniature research reactor neutron source M.S 1401/06/30
mohammad javad keikhafarzaneh SURVEY OF IMAGE QUALITY AND PATIENT DOSES IN CONVENTIONAL X-RAY EXAMINATIONS ESTABLISHING GUIDANCE LEVELS AND COMPARISON WITH INTERNATIONAL STANDARDS IN SISTAN AND BALOCHESTAN PROVINCE M.S 1387/12/10
Nourollah Khajvand Neutronic conceptual design of cold neutron source in Tehran research reactor M.S 1393/09/25
somayeh khalili Neutron Source Designing For Boron Neutron Capture Therapy Using D-T Accelerator M.S 1390/11/10
Sara Masjedian jazi In-core neutron and gamma monitoring of Bushehr nuclear reactor M.S 1395/09/17
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
Seyedmohammad mirvakili طراحی وتوسعه شبیه سازی شبکه عصبی برای پیشگویی پرامترهای حالت پایدار یک راکتور vver-1000 نوعی با استفاده از کوپلینگ کدهای mcnp , cobra برای محاسبه اثرات نوترونیک و ترموهیدرولیک Ph.D 1391/07/12
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
saeed mohammadi Investigation of 99Mo production using a unique procedure of natural uranyl sulphate and uranyl nitrate liquid target irradiation by proton cyclotron accelerator M.S 1396/06/29
Mohammad Mehdi Mohammadi Calculation of Temperature Coefficients of a Gas Cooled Fast Breeder Reactor M.S 1393/06/26
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
Javad Mokhtari Design of a low-power reactor for BNCT,NR and NAA and Construction OF a thermo-hydraulic Test-Loop Ph.D 1396/02/26
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
seyedehmojgan mousavi Calculation of received I-131 dose to the thyroid of the working personel in the forbidden zone of the Bushehr NPP M.S
Seyed milad Mousavi Burn up Analysis of Annular Fuel Pins in VVER-1000 using Hydride or Conventional Solid UO2 Fuel M.S 1391/10/16
manouchehr navvabi Measurement of Heavy Metals Concentration in Iranian Tea Leaves Using Neutron Activation Analysis M.S 1399/06/31
Narsis Nejat Conceptual design on the fuel of RTG for in-planets space traveling M.S 1392/09/30
fatemeh nikseresht Evaluation of the implementation of radiation protection principles in diagnostic radiology and CT-scan departments of the Fars province M.S 1398/11/27
Amin Nobakht Determination of the best energy for in-vivo measurement of bone lead by X-ray fluorescence spectroscopy method using Monte Carlo simulation M.S 1397/06/31
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
mohammad hadi porhemmat Investigation of Transient States in VVER-1000 Bushehr Reactor Using PARCS Code M.S 1392/06/30
zahra rezaei Developing a protocol for eye lens dosimetry of radiation workers in angiography and fluoroscopy departments M.S 1400/11/15
Fatemeh Roosta Developing dynamic event tree for SGTR accident in unit 1 BNPP Ph.D
Amir Sadeghnoedoost Neutronics Study of a Small Modular Reactor Core Using Monte Carlo Method. M.S 1397/05/16
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
Mohsen Safarinia Secondary shutdown system design using heavy water tank in open pool research reactors M.S 1393/09/25
mostafa saidi nezhad Annular Fuel Design and its Applications in a PWR M.S 1389/09/02
farhad salari Assessment of the core corium catcher safety system for typical VVER-1000 nuclear reactor during severe accidents Ph.D 1400/06/31
hamed sohrabi Systematic designing for increasing thermal neutron flux in a specific direction and geometrical optimization of neutron activation using Pu-Be neutron source M.S 1392/06/23
mahmood tahmasebi Design and Optimization of a Flat-Panel X-ray Source Using Gate Monte Carlo Code M.S
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
حیدر حیدری داد Single Phase Natural Circulation Study of a Rectangular Loop Using Numerical Techniques and RELAP5/MOD3 Code M.S 1386/06/28
محمود خزایی MONITORING ON THE ENRICHMENT PLANT INCLUDING ENVIRONMENTAL AS WELL AS PERSONNEL DOSIMETRY M.S 1387/09/15
The Evaluation of Lithiated Polyethylene & a typical mineral compound neutron shield properties with d+T &d+D neutron sources by experiment and MCNP calculation M.S 1387/05/07
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
Thermo Hydraulic Analysis of a Typical Research Reactor Fuel Assembly by CFD Method M.S 1387/04/31
Simulation of Power and reactivity control in a research reactor M.S 1383/06/01
Design and Implementation of a Risk Monitor and its Application for a Typical Research Reactor M.S 1385/02/27
MUSEUM AND INFORMATION CENTER OF IRAN ATOMIC ORGANIZATION M.S 1387/11/26
A Survey On The Photoactivation Effect Of Cisplatin Drug On Dose Enhancement In Malignant Tumors M.S 1387/06/27
yasaman abolghasemi Design of a Monte-Carlo Algorithm for the PNI Imaging System M.S 1399/06/31
Ali Abrar Numerical investigation of the boiling phenomenon of two successive droplets impacting on an oblique hot solid surface M.S 1397/11/30
shaghayegh adibpoor Evaluation of the Effect of Scattering, Attenuation and Detector Geometry on the Quality of Polarized Nuclear Imaging (PNI) System Using GEANT 4 Monte- Carlo Code M.S 1400/06/31
Mahtab Adine Quantitative Evaluation of Void Fraction in Two Phase Flow inside Vertical Tubes by Gamma-Ray M.S 1391/05/24
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
mohsen akbarzadeh Application of DRAGON to standard NEA benchmark and development of user interface for input geometry module in DRAGON M.S 1391/07/30
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
Fahimeh Asadian aa M.S 1389/12/25
Navid Ayoobian محاسبه ترادبرد الکترون فوتون توسط کتابخانه epdl97 و الگوریتم smart برای پدازشگرهای موازی Ph.D 1390/11/27
B. Azadbakht Response verification of a (MAGICA, PAGAT…) gel dosimeter by radiation systems with a medical imaging system M.S 1386/06/20
Bahador Bahadorzadeh Simulation, Design and Construction of Bonner Spheres for Neutron spectromtry M.S 1392/07/03
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
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
maryam farajpour Dynamic Assessment of Core Damage Frequency by Fire Initiating Event in Tehran Research Reactor Building Ph.D
Tahereh Farzaneh Application of DWT for quantitative evaluation of computational data from thermo hydraulic codes M.S 1390/12/23
kobra fatehimarj Analysis of natural circulation in residual heat removal for a typical prissurized water reactor M.S 1390/12/14
Mohammad Esmaeil Fazilat Moaddeli Optimization of X-ray Spectrum in Dual Energy CT Scan Ph.D 1398/02/25
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
sayed fazel ghazi ardekani EXACT STUDIES ON SAFETY-EMERGENCY SYSTEM OF NUCLEAR REACTORS MODEL VVER-1000(V-320) AND ITS COMPARISON WITH BUSHEHR NUCLEAR POWER PLANT MODEL VVER-1000(V-446) M.S 1387/07/13
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
Sajjad Hassanpour Graphical User Interface Design for DRAGON Code and Resonance Self-shielding Effect Calculations for Fuel of Bushehr Nuclear Power Plant-Unit II (BNPP-II) Using DRAGON Code M.S 1400/11/15
arash izadi Development of Esfahan MNSR reactor’s Dead-time calculation code considering poisons built up and temperature feedback M.S 1400/11/15
shahab addin kamyab Risk monitoring software designing to evaluate AP1000 PCCS Reliability Improvement with due to Redundancy and CCFs M.S 1389/06/01
mohamad karamy Indoor Radon Concentration in Dwellings of Yazd province M.S 1388/06/31
zahra kowsar Application of Nanofluids as Reactivity Control and Heat Transfer Enhance in a Typical Light Water Reactor M.S 1393/11/29
Mohamad Hasan Mahdian Manesh Development of an image reconstruction software with application in the industrial computed tomography M.S 1397/11/24
mohammadhossein mirzamohammadzadeh Development of SOEP procedures for VVER-1000/446 nuclear reactor in SBLOCA accident using RELAP5 code Ph.D 1401/06/29
zahra mokhtari homami EVALUATION OF PRIMARY SAFETY PARAMETERS FOR A STORAGE FACILITY OF UF6 CYLINDERS M.S 1389/06/31
Leila Moradi DNB Analysis of a Hot Channel with Grid Spacer and Mixing Vanes in Presence of Nanofluid Coolant M.S 1395/06/08
V. moslemi CT- BASED TREATMENT PLANNING USING MONTE CARLO SIMULATION M.S 1386/06/31
cousar nassiry hanis MR CHARACTERIZATION OF BRAIN TISSUE USING M.S 1388/06/31
Mohammad Nazififard THE EFFECT OF FUEL ASSEMBLY SPACER GRIDS ON HEAT TRANSFER PARAMETERS IN A TYPICAL PWR CORE M.S 1385/10/05
fateme nowroozalizadeh Investigation and Determination of Diagnostic Reference Levels in Fars Province and comparing them to other International and National Guidance Levels M.S 1390/07/04
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
A. Piroozmand مدل سازی وحل معادلات سینیتیک حاکم بر قلب راکتور هسته ای با استفاده از شبکه عصبی سلولی چند لایه ای M.S 1385/06/01
Mohammadhadi Porhemmat Development and implementation of whole-core neutron transport calculation methods for highly heterogeneous core Ph.D 1397/11/30
abbas pourdarab Evaluation of Environmental air pollution in Mouk area in Firouzabad, Iran using Neutron Activation Analysis M.S 1388/06/01
mohsen pourramezanshahabaldini Development of a model for radial burnup calculation in VVER-1000 reactor fuel rod using Monte Carlo method M.S 1401/11/15
Meysam Rafiei Design of optimized FOPID controller system in load following operation based on the two-point FNPK model for PWR nuclear reactors Ph.D 1398/08/21
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
Majid Razeghianjahromi Simulation and Evaluation of a Typical Nuclear Fuel Manufacturing Plant Safety Level in Fire Accidents M.S 1390/04/19
mojtaba rezaii Atmospheric dispersion assessment of radionuclides due to severe accident in spent fuel pool of BNPP-1 using HYSPLIT code M.S 1402/06/26
parastou roustazadeh sheikh usefi Assessment of radioactive dispersion from a hypothetical 5 MW nuclear reactor under normal operation and after an accident in TEHRAN M.S 1392/06/27
Hassan Saadati An Optimal Controller for Power Maneuvering in NuScale SMR Using Artificial Neural Network and Implementing HGAPSO Algorithm Ph.D
seyed ali sadrzadeh rouholamini Study of the effects of long term occupational exposure of EMFs in workers of high tension stations M.S 1392/06/30
Saiedeh Safaei Arshi Probabilistic safety assessment of fire at Tehran research reactor containment M.S 1386/12/20
rasool safari Conceptual Design of a Few Photons Medical Imaging System: Interactional Ghost Imaging Ph.D 1402/12/16
Rasool Safari Feasibility Study of Quantum Imaging by Gamma Ray M.S 1395/10/29
Samira Sarshough Determination of low energy X-rays cross sections for nano and micro reinforced epoxies and comparison of their effects in dosimetry calculations Ph.D 1397/03/30
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
seyed mohamad sadegh shobeyri monte-carlo design and simulation of airborne gamma spectrometry in order to achieve better spatial resolution M.S 1392/12/05
tannaz tayebi pour amale Simulation of Electrostatic Accelerator with Deuterium Beam Using Monte Carlo Method. M.S 1398/06/31
maryam_alsadat yousefniaye jahromi Evaluation of Power Peaking Factor in a PWR due to Burn up Transients M.S 1389/04/09
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
leila zare Evaluation of the results of three-dimensional segmentation of the heart in MPI images: comparison between QPS, Corridor 4DM and QCard-nm1 M.S
zahra zare Evaluation of Water Level of VVER-1000/V446 Reactor Pressure Vessel During Severe Accidents Using Cosmic Muon Radiation with Monte Carlo Method M.S 1398/11/30
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
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
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