| | | | |
| 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 |