Determination of Mass Attenuation Coefficients of Different Types of Concretes using Monte Carlo Method

Abstract

Shielding and radiation protection are important subjects for various areas ranging from medical and agricultural sectors to consumer products. As such, it is a branch of science and technology, wherein radiation exposure to the receptor is reduced by shielding. In this study mass attenuation coefficients, µ/ρ for some concrete with potential applications in nuclear technology and radiation protection as well as medical physics have been calculated using MCNPX (version 2.4.0) at different photon energy levels. Appreciable variations are noted for mass attenuation coefficients of the concrete by the changes in the photon energy. The MCNPX results are compared with available experimental investigations and theoretical XCOM results, and good agreement is being observed. Present study indicates that MCNPX simulation method is suitable method to be used as an alternative method for the investigation of gamma interaction and would very useful materials for different energies for radiation dosimetry, medical and nuclear technology. 

Keywords

• Concrete,Dosimeter,Attenuation Coefficient,Gamma,MCNPX

Farklı Türdeki Betonların Kütle Zayıflatma Katsayılarının Monte Carlo Metodu ile Belirlenmesi

Abstract

Zırhlanma ve radyasyondan korunma medikal ve tarım sektöründen tüketim ürünlerine kadar oldukça fazla sayıda alan için oldukça önemli bir konu başlığıdır. Bu çalışmada nükleer teknoloji, radyasyondan korunma ve medikal tıp alanında potansiyel kullanıma sahip betonların kütle azaltma katsayılarını, µ/ρ, farklı foton enerjilerinde MCNPX (versiyon 2.6.0) Monte Carlo kodu kullanılarak hesaplanmaktadır. Foton enerjisini değiştirerek betonların kütle azaltma katsayıları için kayda değer farklılıklar kaydedilmiştir. MCNPX sonuçları mevcut deneysel araştırmalar ve teorik XCOM sonuçları ile karşılaştırılmış ve iyi bir uyum gözlenmiştir. Bu çalışma, MCNPX simülasyon yönteminin, gama etkileşiminin araştırılmasında alternatif bir yöntem olarak kullanılacak uygun bir yöntem olduğunu göstermektedir ve radyasyon dozimetresi ve nükleer teknoloji alanında oldukça faydalı materyaller içermektedir.

Keywords

• Beton,Dozimetre,Kütle Azaltma Katsayısı,Gama,MCNPX

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