شماره 4 تاریخ انتشار 2020-08

• Synthesis of strontium borate doped with Pb by solid state method and characterization of its thermoluminescent glow curve
• Design and calibration of a passive detector for separating neutron, proton and alpha particles in mixed radiation fields
• Comparison of Different Model Predictions on RBE in the Proton Therapy Technique Using the GATE Code
• The feasibility of using microstrip gas detector as radon detector for earthquake prediction
• Estimation of neutron effective dose from DD and DT neutron generators and the design of appropriate shield for standing user
• Evaluation of the dose and flux of secondary particles in the lung tissue in breast proton therapy using the Monte Carlo simulation code
• Evaluation of the dose received by women worker in the lung scan centers use 99mTC-MAA by experimental and simulation
• Estimation of neutron and gamma dose in the MNSR research reactor
• Optimization of the rate of production 99Mo-99mTC through fission in the TRR
• Determination of radiological map of radionuclides distribution in soils ‎around of Shazand oil power plant
• Investigation of the required thickness of thorium spent fuel lead transport cask depending on different fuel burnups and cooling times
• Investigation of the Effect of Electron Beam Different Doses on Optical Dissipation in Fiber Optic
• Transition from analogue-to-digital nuclear electronics for precise gamma radiation spectroscopy: advantages and limitations
• Physical Investigation of Space, Dosimetry of Space Ionizing Ray Effect (Van Allen belts, Galactic Cosmic Rays and Solar particles) and Plotting Dose Map for Satellite Circular Missions
• IMPLEMENTATION OF EXTENDED KALMAN FILTER TO REDUCE NON CYCLO-STATIONARY NOISE IN AERIAL GAMMA RAY SURVEY
• Making a novel method to obtain the required irradiation time in fast neutron radiation therapy of liver tissue
• Internal dosimetry of radioiodine using ICRP reference phantoms and updated biokinetic model
• Evaluation of the relative biological effectiveness of the Auger electrons produced during gadolinium neutron capture therapy using microdosimetric approach
• Design and fabrication of cylindrical ionization chamber for application in radiation protection
• Simulation of strand breaks induced in DNA molecule by radiation of proton and Secondary particles using Geant4 code
• Estimating average glandular dose in routine mammography screening using neural network
• Conceptual Design and Simulation of Alpha-Beta Detector for Surface Contamination Measurements
• Determination of virtual point for HPGe detector at various gamma rays energies by simulation and experimental methods
• Investigation of metal hydrides applicability as neutron moderator and shielding by MCNPX
• Designing an approprate solenoid and magnetic field for the HZDR laser-driven beamline
• Photon dosimetry based on selective data sampling for the NaI(TL) detector
• Gamma Irradiation Effect on Asymmetric Giant Magnetoimpedance of Co68.15Fe4.35Si12.5B15 Amorphous Alloy
• Assessment of absorbed dose uncertainty of prostate due to source relocating in brachytherapy by monte carlo method
• Calculation of total dose and dose equivalent distribution in the treatment of lung cancer using MR-guided carbon therapy
• Absorbed dose of Fetus in SPECT-CT Imaging of Mother's Abdomen Regions using Monte Carlo method
• Monte Carlo Simulation of Radiation effects in protection layers of logical cell of the digital gate in ‎the FPGA for electron and proton rays Using the FLUKA Code
• Measurement of Contemporary and Retrospective Radon Concentration in Ramsar Dwellings Using Polycarbonate Detector
• The study of neutron interactions with soft tissue using Monte Carlo simulation using the source PF
• Radiation Safety Assessment of the New Neutron Radiography System at Tehran Research Reactor
• Simulation of environmental dose distribution of nuclear gauge device MC-1DR by MCNPX code
• Investigating the effect of voltage fluctuations on the beam quality of X-rays in the range energy of diagnostic radiology
• Investigation of the relationship between of the Radon Concentration Variation in Reyhanshahr Hot Spring and Earthquakes with D/R >0.5 in that Zone
• Estimation and calculation of radiation dose of copper-64 for nuclear medicine usage
• Compare charged and uncharged particles leakage of plasma focus for medical radioisotopes production
• Simulation of gamma-ray gamma rays by composite shields compared to the lead protection using the MCNPX code
• Determination of the electrical percolation threshold of Polystyrene-Graphene Oxide nanocomposite using the experiment and simulation methods
• Review of techniques for improving the uniformity of dose distribution in total body irradiation (TBI) with parallel – opposed anterior and posterior geometry
• Comparison dose distributions from gamma knife unit 4C with CT data and non-CT data options of beamnrc code
• Developing a software for simulation of gaseous detectors with Monte carlo method in c++ programming language
• Biological Dose Assessment by Chemical Induction of Premature Chromosome Condensation
• The effect of Melatonin pretreatment on growth responses and enhancement of the enzymatic antioxidant system in Chlorella vulgaris under stress of ionizing radiation
• Investigating the Effect of Gamma Ray Source Activity on Down-hole Nuclear Density Tool’s Reading Using Simulation by MCNP Code
• Investigation of penetration depth of 63Ni beta spectrum in silicon by Monte Carlo method and using MCNPX code
• Evaluation of the Factors Related to Exposure Dose of Different Radiographer Groups Working in Isfahan State Hospitals in 2017.
• An approximate analytical solution of the Bethe equation for charged particles in the range of radiotherapy energy
• Introducing a bony composite as tissue equivalent for radiotherapy phantoms
• Classification of Ultra-high Resolution Images using Soft Computing
• Determining the accuracy of measuring the thickness of steel plates using Compton scattering method
• Comparison of Iodine-131 Absorbed Dose and Technetium-99m in Thyroid Scanning Using the MCNPX Simulation Code in the ORNL-MIRD Phantom
• Behavior correction of the inverse square law in irradiation room for volumetric source and detector
• HEPA Filters specifications in two standards, ASME AG-1 & DOE for using in Tehran Research Reactor (TRR)
• Determination of the absorbent dose increase factor for different concentrations of gold nanoparticles using a dosimetry gel