Journal of  Radiation Safety and Measurement

Journal of Radiation Safety and Measurement

The  Journal of Radiation Safety and Measurement (JRSM) is an open access journal that is published quarterly by the Iranian Radiation Protection Society (IRPS) and University of Kashan.

The Radiation Protection Society is the founder of the Iranian Journal of Radiation Safety and Measurement and appoints its Editorial Board.
The  scientific  aspects  of  the  Journal  are  supervised  by  the  Editorial  Board. The Journal is published jointly by the Iranian Radiation Protection Society and the University of Kashan.


Dear respected authors

We got permission to publish English issue. Therefore, all respected authors can also send articles in English.

Current Issue: Volume 15, Issue 2 - Serial Number 58, Summer 2026, Pages 69-127 

Improvement of electron counting of glass-wall Geiger-Muller detector using a verified Monte Carlo method

Pages 109-115

10.22052/rsm.2026.256840.1126

Mohammadamin Asadi, Maryam Hasanvand, Javad Mokhtari, Mohammadhosein Choopan Dastjerdi, Ebrahim Teimoory

Keywords Cloud

  • Dosimetry
  • Thermoluminescence
  • Monte Carlo
  • Simulation
  • MCNPX
  • Brachytherapy
  • Tehran research reactor
  • MCNPX code
  • Monte Carlo simulation
  • MCNP code
  • GEANT4
  • Radiotherapy
  • Absorbed Dose
  • Shielding
  • Radon
  • Gamma ray
  • Nanoparticles
  • Proton therapy
  • Dose
  • Gamma radiation
  • Radiation protection
  • Phantom
  • Geant4-DNA
  • X-Ray
  • Biological dosimetry
  • HPGe detector
  • Gamma Irradiation
  • Monte Carlo method
  • GATE Code
  • GATE
  • Nuclear medicine
  • Dosimeter
  • Plasma focus
  • Neutron
  • MCNP
  • Radioisotope
  • Linear accelerator
  • Magnetic field
  • Proton
  • Treatment planning system
  • detector
  • Plastic scintillator
  • Geant4 code
  • Prostate Cancer
  • Radiation Therapy
  • Internal dosimetry
  • Co-precipitation
  • Quality control
  • HPGe
  • Radiation safety
  • Lung Cancer
  • Radiation Damage
  • Exposure
  • Radiography
  • Radiation dosimetry
  • MCNP4C
  • radiation
  • breast cancer
  • BNCT
  • Gamma
  • Dose Rate
  • Nanoparticle
  • Neutron dosimetry
  • Safety
  • Mass attenuation coefficient
  • Microdosimetry
  • Radon concentration
  • Photoneutron
  • Computed tomography
  • Efficiency
  • ionization
  • Detection
  • Electrical conductivity
  • VVER-1000 reactor
  • Natural radioactivity
  • Alpha
  • SOBP
  • Industrial Radiography
  • Kashan
  • TLD-100
  • Personal dosimetry
  • TLD
  • XCOM
  • Exposure limit
  • Dose distribution
  • Hydroxyapatite
  • MCNPX simulation
  • Image quality
  • Nanocomposite
  • Ionizing radiation
  • Bragg peak
  • Monte Carlo code
  • Dose enhancement factor
  • lineal energy
  • Attenuation Coefficient
  • Calibration
  • Occupational exposure
  • research reactor
  • Radiation shielding
  • Dosimetric parameters
  • optimization
  • Measurement
  • Photoluminescence
  • CaF2:Mn (TLD-400)
  • Gamma-ray
  • RBE
  • Kinetic parameters
  • Radiopharmaceutical
  • Ultraviolet
  • HYSPLIT
  • iodine-131
  • Shield
  • Neutron dose
  • Lithium fluoride
  • Neutron irradiation
  • Total Ionizing Dose
  • Neutron radiography
  • Growth and physiology
  • MNSR reactor
  • Modeling
  • Annual Effective Dose
  • ORNL phantom
  • Flux
  • Ion Beam Analysis
  • MIRD method
  • Impurity
  • Electron Beam
  • Gold Nanoparticles
  • α-Al2O3:C
  • enzymatic antioxdant system
  • Microwave radiation
  • Image Reconstruction
  • neutrons
  • Trajectory
  • Ionization chamber
  • neural network
  • Dose calibrator
  • Film badge
  • Single-strand break
  • Gamma Source
  • Sensitivity loss
  • Polystyrene
  • Relative biological effectiveness
  • double strand breaks
  • PET
  • Dose Assessment
  • Water
  • CT scan
  • EGSnrc code
  • Double Strand Break
  • High dose
  • Fast neutron
  • SPECT-CT
  • Calorimeter
  • Polycarbonate
  • Radiation hazards
  • Surfactant
  • ORNL-MIRD phantom
  • Irradiation time
  • TG-43U1 Protocol
  • Boric Acid
  • Gaseous detector
  • Scintillation
  • Hadron therapy
  • Boron neutron capture therapy
  • Electron Multiplier Assembly (EMA)
  • electron
  • Epoxy resin
  • Ultraviolet radiation (UV)
  • Monte Carlo simulation code
  • Plasma focus device
  • Single Strand Break
  • Boron
  • Retrospective dosimetry
  • Medical Laser
  • Range
  • Radionuclide
  • Rando phantom
  • Electric field
  • dose response
  • Fusion
  • High radioactive
  • Standard limits
  • Fetus
  • Sensitivity
  • Linear dose response
  • Temperature
  • neutron Flux
  • DNA
  • Micro-pattern structure
  • Nuclear accident
  • Variance reduction
  • Strontium-90
  • Melatonin
  • Thermal neutrons
  • Uncertainty
  • Satellite
  • Mammography
  • MCNPX Monte Carlo code
  • Protection

Related Journals