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

Urkiye Akar Tarım

Article Details

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

Authors:

Urkiye Akar Tarım

Publisher:

Sakarya University

Main Topics:

Metrology | Applied and Industrial Physics

Journal:

Sakarya University Journal of Science Vol.27 Issue 1, pp.159-167

Document Type:

Article

Publication Date:

2/2023

Document Language:

English

Document ID (Org No.):

2001283962

pISSN:

2147-835X

Keywords:

Abstract:

 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 epoxymagnetiteboron 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.

 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 epoxymagnetiteboron 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.

 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 epoxymagnetiteboron 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.

 Nükleer teknolojide uzun zamandır gamaların zırhlanmasına yönelik yaygın olarak kullanılan kurşunun toksisitesi ve çevreye olumsuz etkileri göz önünde bulundurularak, son zamanlarda gama radyasyonunun zırhlanmasında kurşuna alternatif olarak kullanılabilecek çeşitli kalkan malzemelerinin geliştirilmesine ilişkin çalışmalara yönelinmiştir. Bu araştırmada, manyetit ve bor karbür içeren kompozit bir malzeme epoksimanyetitbor karbür ile nükleer uygulamalarda üzerinde önemle durulan gama transmisyon tekniği kullanılarak gama ışını zırhlamasına yönelik olarak çalışılmıştır. Bu teknik için ele alınan radyasyon kaynakları, nükleer teknolojide önemli olan Am-241, Cs-137, Na-22 ve Co-60 radyoizotoplarıdır. Söz konusu kompozit malzeme ile 59.5, 511, 661.6, 1173.2, 1274.5 ve 1332.5 keV enerjili gamaların etkileşmeleri Monte Carlo yöntemi ile ayrı ayrı incelenmiş, malzemenin bu enerjilerdeki radyasyonları zırhlama kabiliyeti araştırılmıştır. İncelenen kompozitin radyasyon zırhlama parametreleri arasında olan lineer zayıflama katsayısı, ortalama serbest yol, yarıdeğer kalınlığı ve ondabir değer kalınlık değerlerinin belirlenmesi amacıyla yazılan Monte Carlo kodunda yayınlandıkları noktadan itibaren sistemi terk edene kadar sistemden kaçma veya soğurulma yoluyla gama ışınları, tek tek, tesir kesitleri kullanılarak ortamla etkileşme olasılıkları belirlenerek takip edilmiştir. Modelleme sonuçları kullanılarak hesaplanan zırhlama parametreleri, XCOM yazılımından elde edilen veriler kullanılarak da hesaplanmış, sonuçların birbirleriyle uyumlu olduğu görülmüştür. Diğer taraftan, ele alınan kompozitin çalışılan enerji aralığında nükleer uygulamalar için alternatif zırh malzemesi olarak kullanılabilirliğinin daha iyi değerlendirilebilmesi için çeşitli malzemelere ait, literatürde mevcut olan zırhlama parametreleri ile karşılaştırma yapılmıştır.

Article Details

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

Authors:

Urkiye Akar Tarım

Publisher:

Sakarya University

Main Topics:

Metrology | Applied and Industrial Physics

Journal:

Sakarya University Journal of Science Vol.27 Issue 1, pp.159-167

Document Type:

Article

Publication Date:

2/2023

Document Language:

English

Document ID (Org No.):

2001283962

pISSN:

2147-835X

Radiation

gamma ray

shielding

boron carbide

Monte Carlo method

Radyasyon

gama ışını

zırhlama

bor karbür

Monte Carlo yöntemi

Issues

Article Details

Authors: Urkiye Akar Tarım

Publisher: Sakarya University

Main Topics: Metrology | Applied and Industrial Physics

Journal: Sakarya University Journal of Science Vol.27 Issue 1, pp.159-167

Document Type: Article

Publication Date: 2/2023

Document Language: English

Document ID (Org No.): 2001283962

pISSN: 2147-835X

Issues

Authors:

Urkiye Akar Tarım

Publisher:

Sakarya University

Main Topics:

Metrology | Applied and Industrial Physics

Journal:

Sakarya University Journal of Science Vol.27 Issue 1, pp.159-167

Document Type:

Article

Publication Date:

2/2023

Document Language:

English

Document ID (Org No.):

2001283962

pISSN:

2147-835X