Shielding Effect of Aluminum Against Cs-137 Source, According to Gamma Ray Transmission Technique

Öz

In this study the shielding effect of the Aluminum element against radiation is referred to by using the gamma ray transmission technique. Selected gamma-ray source Cesium is monoenergytic and not necessary the activity correction due to its half-life. Absorption caused by aluminum leads to a reduction in the radiation dose exposed. In the literature, there are many studies on this technique using different materials. Our experiments were carried out with aluminum samples of different thicknesses. Density values are calculated through counts obtained using the Scintillation detector is used in order to get intensity values via counts. By increasing the thickness of the sample from a minimum of 0.49 cm to a maximum of 2.29 cm, the [I/Io] ratio is respectively; 0.8995; 0.8134; 0.7170 and 0.6413 calculated. The curve of variation of the ratio [I/Io] for different thicknesses is given in the graph. R2 value was obtained as 0.9960. The linear absorption effect is accurately observed. Another issue is; in industrial applications, using these intensity ratios; material thickness measurements can be made easily.

Anahtar Kelimeler

• Cs-137
• absorption/attenuation
• aluminum; gamma-transmission technique
• nuclear applications

Kaynakça

1. [1] Turgay M. E., "Density assessment of different metals and alloys by gamma ray transmission technique via using Co-60 radioactive source", Journal of Pyhsical Science and Application 7 (2017) : 39-42.
2. [2] T. Bjonsat, Stamatakis, E., "Scaling studies with gamma transmission technique", Conference: Oil Field Chemistry, Geilo- Norway (2006) : 1- 14.
3. [3] El-Khayatt A. M., "NXcom-A program for calculating attenuation coefficients of fast neutrons and gamma- rays", Annals of Nuclear Energy 38 (2011) : 128-132
4. [4] Elmahroug Y, Tellili B, Souga C., "Calculation of gamma and neutron shielding parameters for some materials polyethylene-based", International Journal of Physics and Research 3 (2013) : 33-40.
5. [5] Büyük B., Tugrul A. B., "Investigation on Gamma Attenuation Behaviour of Titanium Diboride Reinforced Boroncarbide-Silicon", Radiation Physics and Chemistry 97 (2014) : 354-359.
6. [6] Büyük, T., "Investigation on the behaviours of TiB2 reinforced B4C-SiC composites against Co-60 gamma radioisotope source", PAU- Engineering Science Journal 21 (2015) : 24-29.
7. [7] Buyuk, B., "Cs-137 gamma ray attenuaiton properties of flexible silicone rubber materials", Europian Journal of Science and Technology (EJOSAT) 15 (2019) : 18-27.
8. [8] Turgay, M. E., "Comparison of gamma sources (cobalt and cesium) for density measurement of metals and alloys via using transmission technique", Journal of Technologht and Applied Science 6 (2021) : 37-43.

9. [9] Medhat, M. E., "Application of gamma-ray transmission method for study the properties of cultivated soil", Annals of Nuclear Energy 40 (2012) : 53-59.
10. [10] Moreira, A.C. et al., "Gamma ray transmission technique applied to porous phase characterization of low-porosity ceramic samples", Materials and Structures 46 (2013) : 629-637.
11. [11] Karagöz, B., et al., "Determination of gamma transmittance and density assessment for al doped ZnO thin films by using gamma transmission technique", Defect and Diffusion Forum 312 (2011) : 830-835.
12. [12] Singh, K. et al., "Gamma-ray attenuation coefficients in bismuth borate glasses", Nuclear Instruments and Methods in Physics Research B 194 (2002) : 1-6.
13. [13] A.H. Taqi, H.J. Khalil., "An investigation on gamma attenuation of soil and oil-soil samples", Journal of Radiation Research and Applied Science 10 (2017) : 252-261.
14. [14] Knoll G.F, "Radiation detection and measurement", University of Michigan, John Wiley&Sons Inc. NY (2002).
15. [15] Földiak G., "Industrial application of radioisotopes", Institue Hungarian Academy. Budapest (1986).
16. [16] Gardner, R. P., Ely, R. L., "Radioisotopes measurement applications in engineering", Reinhold Publishing NY (1967).