A peer-reviewed journal published by K. N. Toosi University of Technology

A

  • Abbasi Davani, Fereydoun Experimental study of the cobalt oxide etching rate from metal surface using F2/He atmospheric pressure plasma for decontamination of nuclear components [Volume 5, Issue 2, 2024, Pages 25-32]

  • Abtahi, Seyed Mohammad Mahdi Experimental study on Fricke gelatin gel dosimeters [Volume 5, Issue 1, 2024, Pages 57-61]

  • Aghaie, Mahdi Study of safety parameters of a PWR reactor using Cu nanofluids by molecular dynamics method [Volume 5, Issue 2, 2024, Pages 11-23]

  • Akbari, Morteza Analysis of the control rod withdrawal speed impact on the transient behavior of Bushehr-1 NPP using Simulink software [Volume 5, Issue 1, 2024, Pages 63-74]

  • Asgari, Mansour Investigation and Simulation of Gamma-Neutron Shielding for Nuclear- Pumped Lasers [Volume 5, Issue 1, 2024, Pages 41-47]

  • Askari, Mohammad Experimental study of the cobalt oxide etching rate from metal surface using F2/He atmospheric pressure plasma for decontamination of nuclear components [Volume 5, Issue 2, 2024, Pages 25-32]

  • Azizi Ganjgah, Ali Evaluation of direct and indirect DNA Damage under the Photon Irradiation in the Presence of Gold, Gadolinium, and Silver Nanoparticles Using Geant4-DNA [Volume 5, Issue 2, 2024, Pages 33-41]

B

  • Bakhshzad Mahmoudi, Mehdi Experimental study of the cobalt oxide etching rate from metal surface using F2/He atmospheric pressure plasma for decontamination of nuclear components [Volume 5, Issue 2, 2024, Pages 25-32]

C

  • Choopan Dastjerdi, Mohammad Hossein ‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line [Volume 5, Issue 2, 2024, Pages 43-50]

D

  • Daneshvar, Hamideh Study on Tablet conversion by pressure-less sintering method on the thermoluminescent dosimetric response of Beta Tricalcium Phosphate [Volume 5, Issue 2, 2024, Pages 1-10]

  • Daneshvar, Hamideh Comparison audit program for selected radiotherapy centers by secondary standard dosimetry laboratory (SSDL) using thermoluminescence dosimeter [Volume 5, Issue 2, 2024, Pages 71-75]

  • Darestani Farahani, Nikoo Experimental study of the cobalt oxide etching rate from metal surface using F2/He atmospheric pressure plasma for decontamination of nuclear components [Volume 5, Issue 2, 2024, Pages 25-32]

E

  • Ebrahimzadeh, Reza Computational investigation of 1 up to 3 kCi Co-60 source production at external irradiation boxes of TRR core using MCNPX code [Volume 5, Issue 1, 2024, Pages 1-9]

  • Ebrahimzadeh, Reza ‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line [Volume 5, Issue 2, 2024, Pages 43-50]

  • Edalatkhah, Elham Experimental study on Fricke gelatin gel dosimeters [Volume 5, Issue 1, 2024, Pages 57-61]

  • Edalatkhah, Elham Stability of PVA Fricke gel as a radiochromic indicator for blood irradiation [Volume 5, Issue 1, 2024, Pages 75-80]

  • Eshghi, Mahdi Investigation and Simulation of Gamma-Neutron Shielding for Nuclear- Pumped Lasers [Volume 5, Issue 1, 2024, Pages 41-47]

G

  • Ghahani, Saeed The new design of heavy concrete as neutron and gamma shield using galena, B4C, and nanomaterials [Volume 5, Issue 1, 2024, Pages 49-55]

  • Gholamzadeh, Zohreh Computational investigation of 1 up to 3 kCi Co-60 source production at external irradiation boxes of TRR core using MCNPX code [Volume 5, Issue 1, 2024, Pages 1-9]

  • Gholamzadeh, Zohreh ‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line [Volume 5, Issue 2, 2024, Pages 43-50]

H

  • Hajikhani, Sajad A numerical analysis of the impact of gas pressure and dielectric material on the generation of body force in an air gas plasma actuator [Volume 5, Issue 2, 2024, Pages 51-60]

  • Hajiloo, Nahid Comparison audit program for selected radiotherapy centers by secondary standard dosimetry laboratory (SSDL) using thermoluminescence dosimeter [Volume 5, Issue 2, 2024, Pages 71-75]

  • Hedayat, Afshin A review of advanced Small Modular Reactors (SMRs) through a developed PIRT methodology [Volume 5, Issue 1, 2024, Pages 21-39]

K

  • Kargaran, Hamed A comprehensive approach for calculation of surface area and volume in radiation transport codes [Volume 5, Issue 2, 2024, Pages 61-69]

  • Kavarian, Hora Study on Tablet conversion by pressure-less sintering method on the thermoluminescent dosimetric response of Beta Tricalcium Phosphate [Volume 5, Issue 2, 2024, Pages 1-10]

  • Khoshahval, Farrokh Analysis of the control rod withdrawal speed impact on the transient behavior of Bushehr-1 NPP using Simulink software [Volume 5, Issue 1, 2024, Pages 63-74]

M

  • Mehrabifard, Ramin A numerical analysis of the impact of gas pressure and dielectric material on the generation of body force in an air gas plasma actuator [Volume 5, Issue 2, 2024, Pages 51-60]

  • Mirzae Moghadam, Iman The new design of heavy concrete as neutron and gamma shield using galena, B4C, and nanomaterials [Volume 5, Issue 1, 2024, Pages 49-55]

  • Moghtader, Soheil Comparison audit program for selected radiotherapy centers by secondary standard dosimetry laboratory (SSDL) using thermoluminescence dosimeter [Volume 5, Issue 2, 2024, Pages 71-75]

  • Mohammadi, Mostafa Comparison audit program for selected radiotherapy centers by secondary standard dosimetry laboratory (SSDL) using thermoluminescence dosimeter [Volume 5, Issue 2, 2024, Pages 71-75]

  • Mokhtari, Javad ‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line [Volume 5, Issue 2, 2024, Pages 43-50]

  • Mosayebi, Armin Study on Tablet conversion by pressure-less sintering method on the thermoluminescent dosimetric response of Beta Tricalcium Phosphate [Volume 5, Issue 2, 2024, Pages 1-10]

N

  • Naghshnejad, Zeinab Computational investigation of 1 up to 3 kCi Co-60 source production at external irradiation boxes of TRR core using MCNPX code [Volume 5, Issue 1, 2024, Pages 1-9]

  • N. Ghodsi, Omid Comparison audit program for selected radiotherapy centers by secondary standard dosimetry laboratory (SSDL) using thermoluminescence dosimeter [Volume 5, Issue 2, 2024, Pages 71-75]

  • Nobakht, Parisa The new design of heavy concrete as neutron and gamma shield using galena, B4C, and nanomaterials [Volume 5, Issue 1, 2024, Pages 49-55]

P

  • Pourimani, Reza The new design of heavy concrete as neutron and gamma shield using galena, B4C, and nanomaterials [Volume 5, Issue 1, 2024, Pages 49-55]

  • Pourranjbar, Farshid Experimental study on Fricke gelatin gel dosimeters [Volume 5, Issue 1, 2024, Pages 57-61]

  • Pourrostam, Amir Computational investigation of 1 up to 3 kCi Co-60 source production at external irradiation boxes of TRR core using MCNPX code [Volume 5, Issue 1, 2024, Pages 1-9]

S

  • Sedighi, Mahsa Stability of PVA Fricke gel as a radiochromic indicator for blood irradiation [Volume 5, Issue 1, 2024, Pages 75-80]

  • Shamsinasab, Mehrdad Investigation and Simulation of Gamma-Neutron Shielding for Nuclear- Pumped Lasers [Volume 5, Issue 1, 2024, Pages 41-47]

  • Shayesteh, Mohsen Benchmark MCNP computer code simulation results against experimental data of neutron flux and spectrum from neutron imaging system of Tehran research reactor [Volume 5, Issue 1, 2024, Pages 11-19]

  • Soltani Ahmadi, Hamed A numerical analysis of the impact of gas pressure and dielectric material on the generation of body force in an air gas plasma actuator [Volume 5, Issue 2, 2024, Pages 51-60]

T

  • Taherparvar, Payvand Stability of PVA Fricke gel as a radiochromic indicator for blood irradiation [Volume 5, Issue 1, 2024, Pages 75-80]

  • Taherparvar, Payvand Evaluation of direct and indirect DNA Damage under the Photon Irradiation in the Presence of Gold, Gadolinium, and Silver Nanoparticles Using Geant4-DNA [Volume 5, Issue 2, 2024, Pages 33-41]

Z

  • Zahian, Ali Study of safety parameters of a PWR reactor using Cu nanofluids by molecular dynamics method [Volume 5, Issue 2, 2024, Pages 11-23]

  • Zamani, Majid Benchmark MCNP computer code simulation results against experimental data of neutron flux and spectrum from neutron imaging system of Tehran research reactor [Volume 5, Issue 1, 2024, Pages 11-19]