K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
Investigation of the water to air conversion factor dependency to the spent fuel cooling time, irradiation history and burnup for gamma dose rate determination of TRR spent fuels
1
7
EN
Zohreh
Gholamzadeh
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
cadmium_109@yahoo.com
Rohollah
Adeli
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
radeli@aeoi.org.ir
Mahdi
Keivani
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
mkeivani@aeoi.org.ir
10.22034/rpe.2021.242746.1021
Routine gamma dosimetry of spent fuels in nuclear power stations is mandatory to manage their storage in dry or wet spent fuel storages. Mostly the spent fuel gamma dose rate measurements out of the spent fuel pool is impossible because of the high exposures of the operators. Therefore, determination of a conversion factor as precise as possible is important that could be applied to convert the measured gamma dose rate inside the water shield to the air values. Simulation methods are powerfully applied to investigate the conversion factor variation trends due to different burnup, cooling time and irradiation history of the spent fuels. The present work uses MCNPX Monte Carlo-based code to determine the trend. The obtained results of this computational study showed that the conversion factor would not have any dependency to the cooling times, burnup values and irradiation history if the detector is placed at special positions in air or water environments. Comparison of the simulation and experimental data showed an acceptable conformity, so that the experimental verified the simulation data trend
Gamma dose rate,Conversion factor of air to water,Computational calculations,ORIGEN code,MCNPX code
https://rpe.kntu.ac.ir/article_125528.html
https://rpe.kntu.ac.ir/article_125528_57f95605f50151bb0fc9b4b6673c1fc1.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
Feasibility study of Mo-99 production using high-power electron Linac: Nuclear and thermal-mechanical analysis based on photoneutron interaction
9
17
EN
Ali
Taaghibi Khotbesara
Department of Physics, K.N. Toosi University of Technology, Tehran, Iran
khotbesara@email.kntu.ac.ir
Faezeh
Rahmani
Department of Physics, K.N. Toosi University of Technology, Tehran, Iran
frahmani@kntu.ac.ir
Farshad
Ghasemi
Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
farshad.ghasemi@gmail.com
10.22034/rpe.2021.252856.1026
This work presents an alternative method for Mo-99 production as a parent nuclide of Tc-99m which is the most used radioisotope in diagnostic imaging processes. Regarding to some benefits of accelerator-based methods over reactor-based methods for Mo-99 production, the electron Linac-based method has been selected. In this way of production, two approaches (one-stage and two-stage) are available using photoneutron reaction in Mo-100 target using bremsstrahlung photons. The superiority of one-stage approach and optimal dimension of target has been demonstrated by nuclear simulation using MCNPX2.6 code. Thermal analysis of the optimized target has been performed by COMSOL software, which has been led to select the indirect cooling system. The final suggested conceptual design of the target includes nine Mo-100 stripe plates with 0.2, 3, and 30 cm in thickness, width and length, respectively which being surrounded by two copper clamps as the cooling ducts. The velocity of 2.5 m/s of inlet coolant (water) is sufficient for the suggested cooling system to satisfy the conditions of the turbulent regime as the desired cooling regime.
Mo-99 production,Electron linear accelerator,photoneutron,Monte Carlo MCNPX2.6 code,COMSOL
https://rpe.kntu.ac.ir/article_125526.html
https://rpe.kntu.ac.ir/article_125526_5cbd9bf78f916bf7b7cf171cfafb57c3.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
Studies on Photon Buildup of the Dysprosium Doped Lithium Magnesium Borate Glasses System
19
25
EN
Mahdi
Eshghi
0000-0002-5900-7683
Department of Physics, Imam Hossein Comprehensive University, Tehran, Iran
eshgi54@gmail.com
10.22034/rpe.2021.249869.1023
The buildup factor is becoming a required parameter for exposure and energy absorption in the area of radiation physics for shielding, dosimetry, health physics and medical physics. In this research, photon buildup for dysprosium doped lithium magnesium borate glasses system has been investigated. Photon energy absorption buildup factors and photon exposure buildup factors were computed for the chosen glasses using the five-parameter geometric progression fitting method in energy range of 0.015 MeV to 15 MeV. Also, effective and equivalent atomic numbers were calculated for these compositions and discussed for possible implementation in radiation dosimetry.
EBF,EABF,Ionization radiation,Radiation dosimetry
https://rpe.kntu.ac.ir/article_125529.html
https://rpe.kntu.ac.ir/article_125529_e837c1c9875918a35cb7b46620242ac2.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
Dosimetric investigation of esophageal stents carrying I-125 seeds for the treatment of advanced esophageal cancer
27
33
EN
Payman
Rafiepour
0000-0003-2221-5822
Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran
p.rafiepour72@gmail.com
Shahab
Sheibani
Nuclear Science Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
ssheibani@aeoi.org.ir
Daryiush
Rezaey Uchbelagh
Department of Energy Engineering and Physics, Amirkabir University of Technology, Tehran, Iran
ddrezaey@gmail.com
Hossein
Poorbaygi
Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran
hpoorbaygi@gmail.com
10.22034/rpe.2021.202211.1025
Radioactive stents loaded with I-125 seeds have been widely used for the treatment of advanced esophageal cancer. Understanding the dose distribution of such stents before the clinical use is essential. This study provides a dosimetric investigation of I-125 seed-loaded stents based on the seed's arrangement and activity. A cylindrical water equivalent phantom with an esophageal stent loaded with I-125 seeds, were employed. The seeds arrangements were determined based on the distance between the centers of two adjacent seeds (z) along the stent length. EBT3 films as well as Geant4 Monte Carlo toolkit were used to obtain the dose distribution around the stent. By modeling the MIRD phantom, the dose delivered to the related organs at risk was calculated. The appropriate dose distribution is achieved for z=15 mm, in which the absorbed dose at a depth of 5 mm reaches about 45% of the absorbed dose near the stent surface, thereby the therapeutic dose is delivered to the reference points. Both arrangements (z=15 and 20 mm) seemed to be clinically eligible and their utilization depends on the patient and the hospital facilities. Using esophageal stents with z>20 mm is not recommended due to the presence of cold spots in the dose distribution.
Esophageal Cancer,Radioactive stent,Brachytherapy,Dosimetry,Monte Carlo
https://rpe.kntu.ac.ir/article_125530.html
https://rpe.kntu.ac.ir/article_125530_323a677f6ac6d84a66671451768121e0.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
Feasibility study of application of ThO2 fuel rods in VVER-1000 fuel assemblies using MCNP and ORIGEN codes
35
41
EN
Zohreh
Gholamzadeh
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
cadmium_109@yahoo.com
Atieh
JozVaziri
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
vaziri.atiyeh63@gmail.com
10.22034/rpe.2021.242881.1022
Thorium is more abundant in nature than uranium. The fertile thorium fuel can breed to fissile U-233 by absorbing a neutron. The produced fissile has good neutronic performance in both thermal and fast neutron spectra. Many types of thorium-based fuels were applied in different nuclear reactors. Also natural thorium oxide is used as seed/blanket configuration that the ThO<sub>2</sub> rods are used in the outer sections of any fuel assembly. The present study aims to investigate the ThO<sub>2</sub> fuel rod loading in 3000 MW VVER-1000 power reactor. MCNPX and ORIGEN codes were used to evaluate its effects on the core neutronic. In addition, the gamma emission rates of ThO<sub>2</sub> spent fuel than the UO<sub>2</sub> routine fuel of VVER-1000 was investigated. The obtained results of the computational study showed the ThO<sub>2</sub> fuel rod loading in some VVER-1000 fuel assemblies would not end to a breeding behavior of the reactor core even after one-year burnup at 3000 MW power. However, the enriched uranium fuel loading reduction may make a motivation for thorium fuel application in the power reactor.
Power reactor,Thorium fuel,Burnup,Gamma emission rate,Computational calculations
https://rpe.kntu.ac.ir/article_125531.html
https://rpe.kntu.ac.ir/article_125531_4417512498684a366eda6f1a4deae6e1.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
2
1
2021
01
01
A 14 MeV AVF cyclotron magnet design for PET applications
43
48
EN
Berat
Can
Karatas
0000-0002-9965-6370
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
cankaratas@skku.edu
Ho
Namgoong
0000-0002-4551-8714
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
vomlp@skku.edu
Hoseung
Song
0000-0002-5913-3364
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
genesjp@skku.edu
Donghyup
Ha
0000-0002-3866-1686
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
hdh7456@skku.edu
Jong-Seo
Chai
0000-0002-5673-8763
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
jschai@skku.edu
Mitra
Ghergherehchi
0000-0001-5652-4960
Sungkyunkwan University, College of Information and Communication Engineering, Suwon, South Korea
mitragh@skku.edu
10.22034/rpe.2021.250485.1024
A four-sector 14 MeV azimuthally varying field H-type cyclotron magnet has been designed for positron emission tomography (PET) at Sungkyunkwan University. Compactness, feasibility, and high performance are among the main factors that were considered in the design, which is ultimately intended made for use in hospitals and research institutes. After optimizing the initial parameters using the shimming method, an isochronous magnetic field along the cyclotron radius through Opera-3d was investigated. The particle trajectories were also illustrated. The Cyclone equilibrium orbit code program was used to examine the radial and axial betatron oscillations in relation to the cyclotron operating points. In addition, the integrated phase shift was explained and compared to the Korea Institute of Radiological Medical Sciences 13 MeV cyclotron (KIRAMS-13). In conclusion, the final shape magnet satisfied the orbital stability requirements. The RF cavity, vacuum pump, and injection system could be employed efficiently, and a reliable agreement was reached between KIRAMS-13 and our design characterization.
Isochronous cyclotron,Magnet design,Beam dynamics
https://rpe.kntu.ac.ir/article_125532.html
https://rpe.kntu.ac.ir/article_125532_165ea11fa99bc82984cfea37730e78bc.pdf