Application of Monte Carlo Method for Gamma ray Attenuation Properties of Lead Zinc Borate Glasses

Tarim, U. Akar; Gürler, O.

doi:10.16984/saufenbilder.443765

Cited by 4 publications

(2 citation statements)

References 12 publications

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“…Monte Carlo simulation of radiation transport and interaction with matter (distillation column and its contents) was performed, as it is the most reliable way of predicting the effects of gamma rays when they interact with matter [5]. Three prototype distillation columns were modelled in Fluka geometry.…”

Section: Simulation Of Gamma Column Scanningmentioning

confidence: 99%

Gamma Photon Column Scanning of Prototype and Industrial Distillation Columns

Chirume,

Dongo,

Dzingai

et al. 2023

WJET

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Monte Carlo simulation of gamma photon transport and interaction with the distillation column and its contents was performed in order to predict the effects of gamma photons when they interact with matter. The results of the interaction and transport of gamma photons are presented as energy deposition on the distillation column and its contents. Energy attenuation was more pronounced on the column walls and trays as compared to the region between the trays, where there is mostly vapour space. Gamma column scanning was then used to verify the Monte Carlo simulation results by scanning and investigating the integrity of two laboratory prototype distillation and industrial distillation columns. One of the prototype distillation columns was 1 m tall with four trays and the other one was 1.8 m tall consisting of six trays and a packed bed. Commonly encountered distillation column malfunctions such as collapsed tray, weeping, flooding and foaming were simulated in the two prototype distillation columns and scanned. The industrial distillation column was a 26 m tall benzole prefractionator column, consisting of 60 single pass trays and a diameter of 0.8 m. A 10 mCi 60 Co gamma radiation source and NaI(Tl) scintillation detector were used to scan the distillation columns. The results from the two prototypes showed that all the simulated malfunctions were clearly detected except for foaming. The results from industrial distillation column showed that all the trays were in their correct position although tray number 32 could be partially damaged and just below tray 41, the scan revealed that there was a loss of column wall thickness. The obtained density profile for the industrial distillation column showed some small variations from the expected density profile and this was attributed to external features on the distillation column and wind bursts that shifted the source and detector from the chosen scan line orientation.

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Section: Simulation Of Gamma Column Scanningmentioning

confidence: 99%

Gamma Photon Column Scanning of Prototype and Industrial Distillation Columns

Chirume,

Dongo,

Dzingai

et al. 2023

WJET

View full text Add to dashboard Cite

show abstract

“…The attenuation data of the common shielding materials are available at the National Institute of the Standards (NIST) XCOM (McAlister, 2018;Seenappa, Manjunatha, Chandrika, & Chikka, 2017;Mostafa, Issa, & Sayyed, 2017;Yorgun, 2019). Online software calculates the mass attenuation coefficient for alloy and mixture of the material (Erk, Altınsoy, Karaaslan, & Bora, 2016;Tarım, & Gürler, 2018;Ozyurt et al, 2018). In addition to the simulation, the values of the linear attenuation coefficient for each block were calculated from the XCOM software.…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation of the Gamma-Ray Transmissions for the newly Designed Shielding Blocks used in Radiotherapy

Yavuzkanat

Kürem

2020

Journal of Advanced Research in Natural and Applied Sciences

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Radiotherapy is one of the most important treatment methods of cancer, which is the worldwide disease nowadays. It is essential to protect the critical organs and healthy tissue inside the radiated area during the radiotherapy. For this reason, Cerrobend block (lipowitz alloy), which is made specifically for each patient, are commonly used in the hospitals. In the clinical application, the acceptable level of the gamma-ray transmission for Cerrobend blocks must be less than 5%. In this research, GEANT4 based GATE simulation program modelled to compare between gamma-ray transmissions of the standard Cerrobend block and newly designed Cerrobend blocks formed by adding the various number of the pure lead marbles. Experimental measurements were carried out with Alcyon II model Co-60 teletherapy machine for various field sizes by using Farmer type 0,6 cc ion chamber, PTW Unidos Dosimeter and solid phantom in Dr. Abdurrahman Yurtaslan Ankara Oncology Training and Research Hospital in 2010. The gamma-ray transmission of the newly designed Cerrobend block was found less than the standard block, therefore the protection of the critical organs for the patient could be better. The dose acquired by GEANT4 based GATE simulation program is consistent in experimentally measured radiation dose. Furthermore, the values of the linear attenuation coefficient theoretically obtained from XCOM software agree with the values acquired by experiment and simulation.

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Assessment of the Usability of a Composite Containing Boron Carbide for Shielding the Gamma Rays

Tarim

2023

Sakarya University Journal of Science

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Considering the negative effects on the environment and toxicity of lead, which has been widely used for gamma shielding for a long time in nuclear technology, studies have been focused on the development of various materials that can be used as an alternative to lead in gamma radiation shielding. In this research, a composite material containing magnetite and boron carbide (epoxy/magnetite/boron carbide) and gamma transmission technique which is emphasized in nuclear applications have been used for the study of gamma ray shielding. The radiation sources considered for this technique are the radioisotopes Am-241, Cs-137, Na-22 and Co-60, which are important in nuclear technology. The interactions between the composite material and gammas with 59.5, 511, 661.6, 1173.2, 1274.5 and 1332.5 keV energies were investigated separately by the Monte Carlo method, and the ability of the material to shield the radiations at these energies was investigated. Gamma rays, one by one, followed by using cross sections and determining the probability of interaction with the composite from the point they are emitted until they leave the system (through escaping or absorption from the system) in the Monte Carlo code, which is written to determine the linear attenuation coefficient, mean free path, half value layer and tenth value layer, among the radiation shielding parameters of the composite under investigation. The shielding parameters calculated using the simulation results were also calculated using the data obtained from the XCOM software, and the results were found to be compatible with each other. On the other hand, in order to better evaluate the usability of the composite as an alternative shielding material for nuclear applications in the studied energy range, a comparison was made with the shielding parameters of various materials available in the literature.

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Application of Monte Carlo Method for Gamma ray Attenuation Properties of Lead Zinc Borate Glasses

Cited by 4 publications

References 12 publications

Gamma Photon Column Scanning of Prototype and Industrial Distillation Columns

Gamma Photon Column Scanning of Prototype and Industrial Distillation Columns

Monte Carlo Simulation of the Gamma-Ray Transmissions for the newly Designed Shielding Blocks used in Radiotherapy

Assessment of the Usability of a Composite Containing Boron Carbide for Shielding the Gamma Rays

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