A
-
Abundance percent of copper element
Abundance determination of copper in the soil of mine sungun using Neutron activation analysis [Volume 1, Issue 3, 2014, Pages 29-34]
-
Accelerated charged particles
Stopping power of Relativistic accelerated charged particles in laser fusion (ICF) according to collective model [Volume 2, Issue 3, 2015, Pages 48-59]
-
Accidentally Radionuclides Release
Cancer Risk Estimating for Various Organs Du to Accidentally Released Radionuclides from Bushehr Nuclear Power Plant Based on BEIR VII Model [Volume 3, Issue 1, 2016, Pages 53-64]
-
Activity
Abundance determination of copper in the soil of mine sungun using Neutron activation analysis [Volume 1, Issue 3, 2014, Pages 29-34]
-
Activity
Investigation of the moderation effect of water, polyethylene and graphite on Am- Be neutrons by measuring activity of the irradiated samples [Volume 1, Issue 3, 2014, Pages 35-40]
-
AGDE
Determination of radiological parameters of igneous rocks of Alvand zone of Hamadan, Iran [Volume 4, Issue 2, 2017, Pages 1-11]
-
Anneal
Study of the role of dopants and annealing temperature in LiF:Mg,Cu,P [Volume 4, Issue 3, 2017, Pages 34-41]
-
Azeotropic distillation
Investigation of T2O production in Heavy Water production process [Volume 2, Issue 1, 2015, Pages 25-33]
B
-
Backscattering
Measurment of backscattering of 0.662 MeV gamma from the various thickness of the lead, iron and aluminum shield [Volume 1, Issue 3, 2014, Pages 15-22]
-
BDSIM-Geant4
Investigation of electron beam characteristics in ILC BDS beam line by BDSIM_Geant4 code [Volume 4, Issue 1, 2017, Pages 25-32]
-
Beta source
Investigation, analyzing and simulation of single energy making of continues spectrum of beta particle of 90Sr/90Y by using magnetic field of coil [Volume 4, Issue 4, 2017, Pages 48-56]
-
BIER VII Models
Cancer Risk Estimating for Various Organs Du to Accidentally Released Radionuclides from Bushehr Nuclear Power Plant Based on BEIR VII Model [Volume 3, Issue 1, 2016, Pages 53-64]
-
BNCT
Experimental and theoretical feasibility study on the use of TRR medical room for BNCT [Volume 1, Issue 3, 2014, Pages 8-14]
-
Bragg peak
FLUKA simulation of proton dose distribution in water and
brain phantoms [Volume 2, Issue 4, 2015, Pages 28-35]
C
-
Car Inspection
Aboard Dose Assessment in Dual Energy X-ray Vehicle Inspection by Use of Experimental Measurement in Human Rando Phantom [Volume 4, Issue 3, 2017, Pages 10-18]
-
Cask
Nuclear Criticality of Transportation and Storage Cask of Spent Fuel in WWER-1000 Reactor for Two Modes of Burn-Up and Fresh Fuels [Volume 2, Issue 3, 2015, Pages 17-26]
-
Chernobyl accident
Application of the Weibull Distribution Function in Cs-137 Vertical Migration Modelling [Volume 1, Issue 1, 2014, Pages 35-45]
-
COBRA-EN code
Determination of the allowable range of the relative power coefficient distribution in the VVER1000 for a blockage accident [Volume 4, Issue 4, 2017, Pages 1-15]
-
Coincidence
Idintification of emmited gamma from annihilation of positron from 22Na source with measurement of gamma coincidence [Volume 4, Issue 1, 2017, Pages 1-8]
-
Collective Model
Stopping power of Relativistic accelerated charged particles in laser fusion (ICF) according to collective model [Volume 2, Issue 3, 2015, Pages 48-59]
-
Concrete"
Study of concrete additives to improve its protective role against neutron radiation by using MCNPX code [Volume 1, Issue 3, 2014, Pages 1-7]
-
Contrast
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study [Volume 1, Issue 2, 2014, Pages 17-26]
-
Cross section
Investigation of the moderation effect of water, polyethylene and graphite on Am- Be neutrons by measuring activity of the irradiated samples [Volume 1, Issue 3, 2014, Pages 35-40]
-
Cross section
Assessment and Sensitivity Analysis Of the temperature feedback effect in both 70C and 60C library on the Tehran Research Reactor kinetic parameters using the Monte Carlo method [Volume 4, Issue 1, 2017, Pages 47-59]
-
Cs-137
Application of the Weibull Distribution Function in Cs-137 Vertical Migration Modelling [Volume 1, Issue 1, 2014, Pages 35-45]
-
CsI (Tl) Scintillator
Investigation of temperature gradient on the response function of scintillators [Volume 2, Issue 2, 2015, Pages 25-30]
-
CT phantom
FLUKA simulation of proton dose distribution in water and
brain phantoms [Volume 2, Issue 4, 2015, Pages 28-35]
-
Cultural Vase
Neutron radiography for Evaluation of Designs and Defects of Cultural Vase of Samiran at Tehran Research Reactor [Volume 4, Issue 4, 2017, Pages 22-30]
-
Current Gas
Design, Fabrication and Assessment of proportional counter in current and sealed gas mode [Volume 4, Issue 3, 2017, Pages 19-26]
-
Curve fitting
Low Resolution Gamma Spectrums Fitting by Widget Function [Volume 4, Issue 4, 2017, Pages 16-21]
D
-
Deformed Nuclei
study of heavy deformed nuclei properties using Thomas-Fermi model [Volume 2, Issue 4, 2015, Pages 12-17]
-
Densification
Study Of Bushehr VVER-1000 Hot Fuel Rod Mechanical Performance With Rigid Pellet Method. [Volume 4, Issue 1, 2017, Pages 33-46]
-
Disinfection
Study of the mechanisms of gamma rays in purification and disinfection of sewage sludge [Volume 2, Issue 1, 2015, Pages 9-23]
-
Dopant
Study of the role of dopants and annealing temperature in LiF:Mg,Cu,P [Volume 4, Issue 3, 2017, Pages 34-41]
-
Dose
Comparison of two different filter-target combinations effect in breast absorbed dose in mammography and evaluation of influencing factors with MCNPX [Volume 1, Issue 1, 2014, Pages 1-7]
-
Dose
Study of the role of dopants and annealing temperature in LiF:Mg,Cu,P [Volume 4, Issue 3, 2017, Pages 34-41]
-
Dose rate
The Design of a BNCT Treatment Room with a 20MeV Electron Accelerator [Volume 1, Issue 2, 2014, Pages 39-52]
-
Dosimetery
Aboard Dose Assessment in Dual Energy X-ray Vehicle Inspection by Use of Experimental Measurement in Human Rando Phantom [Volume 4, Issue 3, 2017, Pages 10-18]
-
Dosimetr
Study of the role of dopants and annealing temperature in LiF:Mg,Cu,P [Volume 4, Issue 3, 2017, Pages 34-41]
-
Dual Energy Imaging
Aboard Dose Assessment in Dual Energy X-ray Vehicle Inspection by Use of Experimental Measurement in Human Rando Phantom [Volume 4, Issue 3, 2017, Pages 10-18]
E
-
Effluent
Review of the mechanisms of ionizing radiation effect on removal of organic, mineral and microbial pollutants from effluent in combination with different chemicals and photocatalysts [Volume 3, Issue 1, 2016, Pages 15-29]
-
ELCR
Determination of radiological parameters of igneous rocks of Alvand zone of Hamadan, Iran [Volume 4, Issue 2, 2017, Pages 1-11]
-
Elements determination
Abundance determination of copper in the soil of mine sungun using Neutron activation analysis [Volume 1, Issue 3, 2014, Pages 29-34]
-
Energy Loss
Investigation of electron beam characteristics in ILC BDS beam line by BDSIM_Geant4 code [Volume 4, Issue 1, 2017, Pages 25-32]
-
Energy Resolution
Investigation of temperature gradient on the response function of scintillators [Volume 2, Issue 2, 2015, Pages 25-30]
-
Environmental contaminants
Review on some applications of ionizing radiation in water, sewage effluent and sludge refinement on an industrial scale [Volume 4, Issue 2, 2017, Pages 39-51]
F
-
Fission
Study of the fission dynamics of the excited nuclei synthesized in the reaction 18O+192Os in the framework of the Langevin equations [Volume 3, Issue 1, 2016, Pages 8-14]
-
Fission barrier
study of heavy deformed nuclei properties using Thomas-Fermi model [Volume 2, Issue 4, 2015, Pages 12-17]
-
Fission probability
Study of the fission dynamics of the excited nuclei synthesized in the reaction 18O+192Os in the framework of the Langevin equations [Volume 3, Issue 1, 2016, Pages 8-14]
-
Fission Rate
Developing heat transfer and fission rate equations for Fuel Burnup calculations [Volume 2, Issue 2, 2015, Pages 47-52]
-
FLUKA
FLUKA simulation of proton dose distribution in water and
brain phantoms [Volume 2, Issue 4, 2015, Pages 28-35]
-
FORTRAN
Calculation of Radial Temperature, Actinides and Fission Products Variation in a VVER-1000 Fuel Pellet by Monte Carlo Method [Volume 4, Issue 2, 2017, Pages 28-38]
-
Fuel Burnup
Developing heat transfer and fission rate equations for Fuel Burnup calculations [Volume 2, Issue 2, 2015, Pages 47-52]
-
Fuel Rod
Study Of Bushehr VVER-1000 Hot Fuel Rod Mechanical Performance With Rigid Pellet Method. [Volume 4, Issue 1, 2017, Pages 33-46]
-
Fuel rods
Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor [Volume 1, Issue 2, 2014, Pages 1-15]
-
Fuel testing assembly
Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor [Volume 1, Issue 2, 2014, Pages 1-15]
G
-
Gamma source of cesium 137
Measurment of backscattering of 0.662 MeV gamma from the various thickness of the lead, iron and aluminum shield [Volume 1, Issue 3, 2014, Pages 15-22]
-
Gamma Spectroscopy
Low Resolution Gamma Spectrums Fitting by Widget Function [Volume 4, Issue 4, 2017, Pages 16-21]
-
Gamow- Teler transition
Calculation of beta decay rate of 12Be [Volume 1, Issue 3, 2014, Pages 23-28]
-
Garfield
Design and simulation ion chamber to measure the energy intensity of low energy ionizing radiation [Volume 4, Issue 4, 2017, Pages 31-38]
-
Gold Foil
Determination the Strength of a 241Am-Be Neutron Source [Volume 3, Issue 1, 2016, Pages 30-42]
H
-
Heat Transfer Rate
Developing heat transfer and fission rate equations for Fuel Burnup calculations [Volume 2, Issue 2, 2015, Pages 47-52]
-
Heavy metals
Review of the mechanisms of ionizing radiation effect on removal of organic, mineral and microbial pollutants from effluent in combination with different chemicals and photocatalysts [Volume 3, Issue 1, 2016, Pages 15-29]
-
Heavy water reactor
Investigation and modification of power changing effects in HWZPR on the activity of irradiated foils [Volume 2, Issue 3, 2015, Pages 9-16]
-
Hematite
Investigation of Enrichment Process of Radioisotopes in Iron Ore and determination Correlation Coefficient Between Uranium and Thorium Series in them [Volume 2, Issue 3, 2015, Pages 1-8]
-
HOTSPOT software
Cancer Risk Estimating for Various Organs Du to Accidentally Released Radionuclides from Bushehr Nuclear Power Plant Based on BEIR VII Model [Volume 3, Issue 1, 2016, Pages 53-64]
-
HPGe
Determination of Heavy water enrichment using PGNAA method [Volume 2, Issue 4, 2015, Pages 36-42]
-
HPGe detector
Investigation of Enrichment Process of Radioisotopes in Iron Ore and determination Correlation Coefficient Between Uranium and Thorium Series in them [Volume 2, Issue 3, 2015, Pages 1-8]
-
HPLWR
Nano fluid application as a coolant in High performance light water Reactor(HPLWR) [Volume 4, Issue 2, 2017, Pages 20-27]
I
-
ILC
Investigation of electron beam characteristics in ILC BDS beam line by BDSIM_Geant4 code [Volume 4, Issue 1, 2017, Pages 25-32]
-
Image Processing
Mammographic Image Enhancement Using Wavelet Transform [Volume 1, Issue 2, 2014, Pages 53-60]
-
Iodine-131
Synthesis optimization of I-131 radiopharmaceutical encapsulated in the silica magnetic nanoparticles [Volume 1, Issue 1, 2014, Pages 47-53]
-
Ionizing radiation
Study of the mechanisms of gamma rays in purification and disinfection of sewage sludge [Volume 2, Issue 1, 2015, Pages 9-23]
-
Ionizing radiation
Review of the mechanisms of ionizing radiation effect on removal of organic, mineral and microbial pollutants from effluent in combination with different chemicals and photocatalysts [Volume 3, Issue 1, 2016, Pages 15-29]
-
Ionizing radiation
Review on some applications of ionizing radiation in water, sewage effluent and sludge refinement on an industrial scale [Volume 4, Issue 2, 2017, Pages 39-51]
-
Iron ore
Investigation of Enrichment Process of Radioisotopes in Iron Ore and determination Correlation Coefficient Between Uranium and Thorium Series in them [Volume 2, Issue 3, 2015, Pages 1-8]
-
Irradiation
Study of the possibility of using gamma - irradiated sewage sludge in different plants production [Volume 2, Issue 3, 2015, Pages 27-37]
-
Irradiation systems
Review on some applications of ionizing radiation in water, sewage effluent and sludge refinement on an industrial scale [Volume 4, Issue 2, 2017, Pages 39-51]
-
Irradiation with neutron
Abundance determination of copper in the soil of mine sungun using Neutron activation analysis [Volume 1, Issue 3, 2014, Pages 29-34]
-
Irradiation with neutron
Investigation of the moderation effect of water, polyethylene and graphite on Am- Be neutrons by measuring activity of the irradiated samples [Volume 1, Issue 3, 2014, Pages 35-40]
K
-
Keywards: Nuclear Power Plant
Cancer Risk Estimating for Various Organs Du to Accidentally Released Radionuclides from Bushehr Nuclear Power Plant Based on BEIR VII Model [Volume 3, Issue 1, 2016, Pages 53-64]
-
Keywords:Stopping Power
Stopping power of Relativistic accelerated charged particles in laser fusion (ICF) according to collective model [Volume 2, Issue 3, 2015, Pages 48-59]
-
Kinetic parameters
Calculation of kinetic parameters Tehran Research Reactor using MCNPX code and compare the results with perturbation method and reference [Volume 3, Issue 1, 2016, Pages 1-7]
-
Kinetic parameters
Assessment and Sensitivity Analysis Of the temperature feedback effect in both 70C and 60C library on the Tehran Research Reactor kinetic parameters using the Monte Carlo method [Volume 4, Issue 1, 2017, Pages 47-59]
L
-
Lead oxide nanoparticles
Assessment of mass attenuation coefficient of lead nanoparticles for variety of gamma source [Volume 2, Issue 3, 2015, Pages 38-47]
-
Level density parameter
Generalized Superfluid Model in Calculating the Nuclear Level Density Parameters [Volume 1, Issue 1, 2014, Pages 17-23]
-
Limonite
Investigation of Enrichment Process of Radioisotopes in Iron Ore and determination Correlation Coefficient Between Uranium and Thorium Series in them [Volume 2, Issue 3, 2015, Pages 1-8]
-
Liquid-Drop Model
study of heavy deformed nuclei properties using Thomas-Fermi model [Volume 2, Issue 4, 2015, Pages 12-17]
-
LOCA Accident
Calculated and Sensitivity Analysis of Thermohydraulics Parameters of Bushehr Nuclear Power Plant (BNPP) Containment at LOCA Accident [Volume 4, Issue 2, 2017, Pages 12-18]
-
Low resolution Spectrum
Low Resolution Gamma Spectrums Fitting by Widget Function [Volume 4, Issue 4, 2017, Pages 16-21]
-
LSC
Investigation of T2O production in Heavy Water production process [Volume 2, Issue 1, 2015, Pages 25-33]
-
Lung Tissue
Study of Simulation Lung Tissue Nuclear Medicine Images Using SIMIND Software with computer Phantom [Volume 2, Issue 4, 2015, Pages 36-45]
M
-
Magnetic field
Investigation, analyzing and simulation of single energy making of continues spectrum of beta particle of 90Sr/90Y by using magnetic field of coil [Volume 4, Issue 4, 2017, Pages 48-56]
-
Mammographic Images
Mammographic Image Enhancement Using Wavelet Transform [Volume 1, Issue 2, 2014, Pages 53-60]
-
Material Classification
Aboard Dose Assessment in Dual Energy X-ray Vehicle Inspection by Use of Experimental Measurement in Human Rando Phantom [Volume 4, Issue 3, 2017, Pages 10-18]
-
MCNP
Investigation, analyzing and simulation of single energy making of continues spectrum of beta particle of 90Sr/90Y by using magnetic field of coil [Volume 4, Issue 4, 2017, Pages 48-56]
-
MCNP4X
Design and construction of multipurpose moderator with Am-Be neutron source [Volume 1, Issue 1, 2014, Pages 25-34]
-
MCNP code
Design and simulation of a hypothetical system for explosives detection based on PGNAA technique [Volume 2, Issue 4, 2015, Pages 1-11]
-
MCNPX
Experimental and theoretical feasibility study on the use of TRR medical room for BNCT [Volume 1, Issue 3, 2014, Pages 8-14]
-
MCNPX
Light-transport incorporation to MCNP’s PTRAC card for modelling sodium iodide scintillator response to gamma rays [Volume 2, Issue 2, 2015, Pages 1-11]
-
MCNPX2.6
Nuclear Criticality of Transportation and Storage Cask of Spent Fuel in WWER-1000 Reactor for Two Modes of Burn-Up and Fresh Fuels [Volume 2, Issue 3, 2015, Pages 17-26]
-
MCNPX code
Comparison of two different filter-target combinations effect in breast absorbed dose in mammography and evaluation of influencing factors with MCNPX [Volume 1, Issue 1, 2014, Pages 1-7]
-
MCNPX code
Calculation of kinetic parameters Tehran Research Reactor using MCNPX code and compare the results with perturbation method and reference [Volume 3, Issue 1, 2016, Pages 1-7]
-
MCNPX code
Assessment and Sensitivity Analysis Of the temperature feedback effect in both 70C and 60C library on the Tehran Research Reactor kinetic parameters using the Monte Carlo method [Volume 4, Issue 1, 2017, Pages 47-59]
-
MCNPX code
Calculation and Analysis of Neutronic and Kinetic Parameters in NuScale Small Modular Reactor [Volume 4, Issue 1, 2017, Pages 15-24]
-
MCNPX code
Calculation of Radial Temperature, Actinides and Fission Products Variation in a VVER-1000 Fuel Pellet by Monte Carlo Method [Volume 4, Issue 2, 2017, Pages 28-38]
-
MCNPX code
Neutron unfolding using MCNPX code and SAND-II algorithm [Volume 4, Issue 3, 2017, Pages 1-9]
-
MCNPX code
Calculation of neutronic and kinetic parameters in Isfahan Miniature Neutron Source Reactor using Monte Carlo method and comparison with the results SAR [Volume 4, Issue 3, 2017, Pages 42-50]
-
MCNPX simulation
X-ray tube design based on current and voltage of X-ray tube [Volume 4, Issue 3, 2017, Pages 27-33]
-
Medical room
Experimental and theoretical feasibility study on the use of TRR medical room for BNCT [Volume 1, Issue 3, 2014, Pages 8-14]
-
MNSR
Calculation of neutronic and kinetic parameters in Isfahan Miniature Neutron Source Reactor using Monte Carlo method and comparison with the results SAR [Volume 4, Issue 3, 2017, Pages 42-50]
-
Modified Mathematical Morphology
Mammographic Image Enhancement Using Wavelet Transform [Volume 1, Issue 2, 2014, Pages 53-60]
-
Monte Carlo Method
Determination the Strength of a 241Am-Be Neutron Source [Volume 3, Issue 1, 2016, Pages 30-42]
-
Multipole Electromagnets
Investigation of electron beam characteristics in ILC BDS beam line by BDSIM_Geant4 code [Volume 4, Issue 1, 2017, Pages 25-32]
-
Myocardial SPECT
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study [Volume 1, Issue 2, 2014, Pages 17-26]
N
-
NaI Detector
Determination the Strength of a 241Am-Be Neutron Source [Volume 3, Issue 1, 2016, Pages 30-42]
-
NaI(Tl) detector
Measurment of backscattering of 0.662 MeV gamma from the various thickness of the lead, iron and aluminum shield [Volume 1, Issue 3, 2014, Pages 15-22]
-
NaI(Tl) detector
Idintification of emmited gamma from annihilation of positron from 22Na source with measurement of gamma coincidence [Volume 4, Issue 1, 2017, Pages 1-8]
-
NaI(Tl) scintillator
Light-transport incorporation to MCNP’s PTRAC card for modelling sodium iodide scintillator response to gamma rays [Volume 2, Issue 2, 2015, Pages 1-11]
-
Nanofluid
Nano fluid application as a coolant in High performance light water Reactor(HPLWR) [Volume 4, Issue 2, 2017, Pages 20-27]
-
Natural radioactivity
Determination of radiological parameters of igneous rocks of Alvand zone of Hamadan, Iran [Volume 4, Issue 2, 2017, Pages 1-11]
-
NCAT
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study [Volume 1, Issue 2, 2014, Pages 17-26]
-
NEU code
FLUKA simulation of proton dose distribution in water and
brain phantoms [Volume 2, Issue 4, 2015, Pages 28-35]
-
Neutron Activation
Abundance determination of copper in the soil of mine sungun using Neutron activation analysis [Volume 1, Issue 3, 2014, Pages 29-34]
-
Neutron Activation
Determination the Strength of a 241Am-Be Neutron Source [Volume 3, Issue 1, 2016, Pages 30-42]
-
Neutronic and kinetic parameters
Calculation and Analysis of Neutronic and Kinetic Parameters in NuScale Small Modular Reactor [Volume 4, Issue 1, 2017, Pages 15-24]
-
Neutronic and kinetic parameters
Calculation of neutronic and kinetic parameters in Isfahan Miniature Neutron Source Reactor using Monte Carlo method and comparison with the results SAR [Volume 4, Issue 3, 2017, Pages 42-50]
-
Neutronic design
Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor [Volume 1, Issue 2, 2014, Pages 1-15]
-
Neutron moderation
Investigation of the moderation effect of water, polyethylene and graphite on Am- Be neutrons by measuring activity of the irradiated samples [Volume 1, Issue 3, 2014, Pages 35-40]
-
Neutron radiography
Neutron radiography for Evaluation of Designs and Defects of Cultural Vase of Samiran at Tehran Research Reactor [Volume 4, Issue 4, 2017, Pages 22-30]
-
Neutron spectroscopy
Neutron unfolding using MCNPX code and SAND-II algorithm [Volume 4, Issue 3, 2017, Pages 1-9]
-
Non-destructive testing, Image processing
Neutron radiography for Evaluation of Designs and Defects of Cultural Vase of Samiran at Tehran Research Reactor [Volume 4, Issue 4, 2017, Pages 22-30]
-
Nuclear technology
Review on some applications of ionizing radiation in water, sewage effluent and sludge refinement on an industrial scale [Volume 4, Issue 2, 2017, Pages 39-51]
-
NuScale reactor
Calculation and Analysis of Neutronic and Kinetic Parameters in NuScale Small Modular Reactor [Volume 4, Issue 1, 2017, Pages 15-24]
O
-
ORIGEN2.1
Nuclear Criticality of Transportation and Storage Cask of Spent Fuel in WWER-1000 Reactor for Two Modes of Burn-Up and Fresh Fuels [Volume 2, Issue 3, 2015, Pages 17-26]
P
-
Paraffin Wax
Design and construction of multipurpose moderator with Am-Be neutron source [Volume 1, Issue 1, 2014, Pages 25-34]
-
PARCS
Simulation of BNPP steady state by PARCS and PMAXS library [Volume 1, Issue 1, 2014, Pages 9-15]
-
Peak Detection
Low Resolution Gamma Spectrums Fitting by Widget Function [Volume 4, Issue 4, 2017, Pages 16-21]
-
Perturbation method
Calculation of neutronic and kinetic parameters in Isfahan Miniature Neutron Source Reactor using Monte Carlo method and comparison with the results SAR [Volume 4, Issue 3, 2017, Pages 42-50]
-
PGNAA
Determination of Heavy water enrichment using PGNAA method [Volume 2, Issue 4, 2015, Pages 36-42]
-
PGNAA technique
Design and simulation of a hypothetical system for explosives detection based on PGNAA technique [Volume 2, Issue 4, 2015, Pages 1-11]
-
Photomultiplier
Investigation of temperature gradient on the response function of scintillators [Volume 2, Issue 2, 2015, Pages 25-30]
-
PHOTRACK
Light-transport incorporation to MCNP’s PTRAC card for modelling sodium iodide scintillator response to gamma rays [Volume 2, Issue 2, 2015, Pages 1-11]
-
PMAXS
Simulation of BNPP steady state by PARCS and PMAXS library [Volume 1, Issue 1, 2014, Pages 9-15]
-
Pollutants
Study of the possibility of using gamma - irradiated sewage sludge in different plants production [Volume 2, Issue 3, 2015, Pages 27-37]
-
Positron
Idintification of emmited gamma from annihilation of positron from 22Na source with measurement of gamma coincidence [Volume 4, Issue 1, 2017, Pages 1-8]
-
Pre-scission neutron multiplicity
Study of the fission dynamics of the excited nuclei synthesized in the reaction 18O+192Os in the framework of the Langevin equations [Volume 3, Issue 1, 2016, Pages 8-14]
-
Proportional counter
Design, Fabrication and Assessment of proportional counter in current and sealed gas mode [Volume 4, Issue 3, 2017, Pages 19-26]
-
Proton emission
Proton emission from 164,165,166,167Ir،171 Au،177Tl and185 [Volume 4, Issue 4, 2017, Pages 39-47]
-
Proton therapy
FLUKA simulation of proton dose distribution in water and
brain phantoms [Volume 2, Issue 4, 2015, Pages 28-35]
-
PTRAC
Light-transport incorporation to MCNP’s PTRAC card for modelling sodium iodide scintillator response to gamma rays [Volume 2, Issue 2, 2015, Pages 1-11]
-
PWR Westinghouse
Developing heat transfer and fission rate equations for Fuel Burnup calculations [Volume 2, Issue 2, 2015, Pages 47-52]
R
-
Radiopharmaceutical
Synthesis optimization of I-131 radiopharmaceutical encapsulated in the silica magnetic nanoparticles [Volume 1, Issue 1, 2014, Pages 47-53]
-
Raeq
Investigation of Enrichment Process of Radioisotopes in Iron Ore and determination Correlation Coefficient Between Uranium and Thorium Series in them [Volume 2, Issue 3, 2015, Pages 1-8]
-
Reactor Containment
Calculated and Sensitivity Analysis of Thermohydraulics Parameters of Bushehr Nuclear Power Plant (BNPP) Containment at LOCA Accident [Volume 4, Issue 2, 2017, Pages 12-18]
-
RELAP5 code
Numerical Modeling of VVER-1000 Coolant Channels in Transient Core Inlet Flowrate Condition [Volume 1, Issue 2, 2014, Pages 27-37]
-
Resolution
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study [Volume 1, Issue 2, 2014, Pages 17-26]
-
Risk assessment
Study of the possibility of using gamma - irradiated sewage sludge in different plants production [Volume 2, Issue 3, 2015, Pages 27-37]
S
-
Safety
Determination of the allowable range of the relative power coefficient distribution in the VVER1000 for a blockage accident [Volume 4, Issue 4, 2017, Pages 1-15]
-
SANDII
Experimental and theoretical feasibility study on the use of TRR medical room for BNCT [Volume 1, Issue 3, 2014, Pages 8-14]
-
SAND-II code
Neutron unfolding using MCNPX code and SAND-II algorithm [Volume 4, Issue 3, 2017, Pages 1-9]
-
Sealed Gas
Design, Fabrication and Assessment of proportional counter in current and sealed gas mode [Volume 4, Issue 3, 2017, Pages 19-26]
-
Sewage sludge
Study of the mechanisms of gamma rays in purification and disinfection of sewage sludge [Volume 2, Issue 1, 2015, Pages 9-23]
-
Sewage sludge
Study of the possibility of using gamma - irradiated sewage sludge in different plants production [Volume 2, Issue 3, 2015, Pages 27-37]
-
Shielding
The Design of a BNCT Treatment Room with a 20MeV Electron Accelerator [Volume 1, Issue 2, 2014, Pages 39-52]
-
SIMIND
Study of Simulation Lung Tissue Nuclear Medicine Images Using SIMIND Software with computer Phantom [Volume 2, Issue 4, 2015, Pages 36-45]
-
Simulation
Study of Simulation Lung Tissue Nuclear Medicine Images Using SIMIND Software with computer Phantom [Volume 2, Issue 4, 2015, Pages 36-45]
-
Single energy making
Investigation, analyzing and simulation of single energy making of continues spectrum of beta particle of 90Sr/90Y by using magnetic field of coil [Volume 4, Issue 4, 2017, Pages 48-56]
-
Slope fit method
Calculation of neutronic and kinetic parameters in Isfahan Miniature Neutron Source Reactor using Monte Carlo method and comparison with the results SAR [Volume 4, Issue 3, 2017, Pages 42-50]
-
SNR
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study [Volume 1, Issue 2, 2014, Pages 17-26]
-
Solid state Density
Stopping power of Relativistic accelerated charged particles in laser fusion (ICF) according to collective model [Volume 2, Issue 3, 2015, Pages 48-59]
-
SPECT
Study of Simulation Lung Tissue Nuclear Medicine Images Using SIMIND Software with computer Phantom [Volume 2, Issue 4, 2015, Pages 36-45]
-
Spectroscopy
Design, Fabrication and Assessment of proportional counter in current and sealed gas mode [Volume 4, Issue 3, 2017, Pages 19-26]
-
Strain
Study Of Bushehr VVER-1000 Hot Fuel Rod Mechanical Performance With Rigid Pellet Method. [Volume 4, Issue 1, 2017, Pages 33-46]
-
Stress
Study Of Bushehr VVER-1000 Hot Fuel Rod Mechanical Performance With Rigid Pellet Method. [Volume 4, Issue 1, 2017, Pages 33-46]
-
Swelling
Study Of Bushehr VVER-1000 Hot Fuel Rod Mechanical Performance With Rigid Pellet Method. [Volume 4, Issue 1, 2017, Pages 33-46]
T
-
T2O
Investigation of T2O production in Heavy Water production process [Volume 2, Issue 1, 2015, Pages 25-33]
-
Tehran reactor
Assessment and Sensitivity Analysis Of the temperature feedback effect in both 70C and 60C library on the Tehran Research Reactor kinetic parameters using the Monte Carlo method [Volume 4, Issue 1, 2017, Pages 47-59]
-
Tehran Research Reactor
Experimental and theoretical feasibility study on the use of TRR medical room for BNCT [Volume 1, Issue 3, 2014, Pages 8-14]
-
Tehran Research Reactor
Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor [Volume 1, Issue 2, 2014, Pages 1-15]
-
Tehran Research Reactor
Calculation of kinetic parameters Tehran Research Reactor using MCNPX code and compare the results with perturbation method and reference [Volume 3, Issue 1, 2016, Pages 1-7]
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Temperature gradient
Investigation of temperature gradient on the response function of scintillators [Volume 2, Issue 2, 2015, Pages 25-30]
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Temprature feedbacks
Assessment and Sensitivity Analysis Of the temperature feedback effect in both 70C and 60C library on the Tehran Research Reactor kinetic parameters using the Monte Carlo method [Volume 4, Issue 1, 2017, Pages 47-59]
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Thermal–hydraulic analysis
Nano fluid application as a coolant in High performance light water Reactor(HPLWR) [Volume 4, Issue 2, 2017, Pages 20-27]
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Thermoluminescence Intensity
Study of the role of dopants and annealing temperature in LiF:Mg,Cu,P [Volume 4, Issue 3, 2017, Pages 34-41]
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Thomas-Fermi Model
study of heavy deformed nuclei properties using Thomas-Fermi model [Volume 2, Issue 4, 2015, Pages 12-17]
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Titanium dioxide
Review of the mechanisms of ionizing radiation effect on removal of organic, mineral and microbial pollutants from effluent in combination with different chemicals and photocatalysts [Volume 3, Issue 1, 2016, Pages 15-29]
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TK-13
Nuclear Criticality of Transportation and Storage Cask of Spent Fuel in WWER-1000 Reactor for Two Modes of Burn-Up and Fresh Fuels [Volume 2, Issue 3, 2015, Pages 17-26]
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TLD
Aboard Dose Assessment in Dual Energy X-ray Vehicle Inspection by Use of Experimental Measurement in Human Rando Phantom [Volume 4, Issue 3, 2017, Pages 10-18]
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Treatment room
The Design of a BNCT Treatment Room with a 20MeV Electron Accelerator [Volume 1, Issue 2, 2014, Pages 39-52]
V
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Vegetables
Study of the possibility of using gamma - irradiated sewage sludge in different plants production [Volume 2, Issue 3, 2015, Pages 27-37]
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Visual Basic
Calculated and Sensitivity Analysis of Thermohydraulics Parameters of Bushehr Nuclear Power Plant (BNPP) Containment at LOCA Accident [Volume 4, Issue 2, 2017, Pages 12-18]
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VVER1000
Simulation of BNPP steady state by PARCS and PMAXS library [Volume 1, Issue 1, 2014, Pages 9-15]
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VVER-1000 reactor
Numerical Modeling of VVER-1000 Coolant Channels in Transient Core Inlet Flowrate Condition [Volume 1, Issue 2, 2014, Pages 27-37]
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VVER-1000 reactor
Calculation of Radial Temperature, Actinides and Fission Products Variation in a VVER-1000 Fuel Pellet by Monte Carlo Method [Volume 4, Issue 2, 2017, Pages 28-38]
W
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Wavelet Transform
Mammographic Image Enhancement Using Wavelet Transform [Volume 1, Issue 2, 2014, Pages 53-60]
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Weibull distribution function
Application of the Weibull Distribution Function in Cs-137 Vertical Migration Modelling [Volume 1, Issue 1, 2014, Pages 35-45]
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WKB
Proton emission from 164,165,166,167Ir،171 Au،177Tl and185 [Volume 4, Issue 4, 2017, Pages 39-47]
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WWER-1000
Nuclear Criticality of Transportation and Storage Cask of Spent Fuel in WWER-1000 Reactor for Two Modes of Burn-Up and Fresh Fuels [Volume 2, Issue 3, 2015, Pages 17-26]
X
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X-ray inspection system
X-ray tube design based on current and voltage of X-ray tube [Volume 4, Issue 3, 2017, Pages 27-33]
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XRD spectra
Assessment of mass attenuation coefficient of lead nanoparticles for variety of gamma source [Volume 2, Issue 3, 2015, Pages 38-47]
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