Investigation and examination of the behavior of different aluminum alloys against Cs-137 gamma radiozotopic resource

Materials that have always been important in engineering should naturally know their properties and their behavior under various conditions. In this context, the investigation of materials properties, the examination of them and the development of new materials suitable for the purpose constitute the issues that need to be emphasized. On the other hand, it is necessary to know the behaviors of the materials used in these conditions against the radiation even in the conditions of working with nuclear radiation reactors such as the development of nuclear reactors and radiation sterilization. Also, in space technology applications, materials may be exposed to radiation dose in cosmic conditions. In this context, the examination of the behavior of materials against radiation is at the forefront. In this master thesis study, it is aimed to investigate the holding ability of gamma radiation against gamma radiation of aluminum alloys, which are considered as an important usage place in the industry. Aluminum is a preferably used material for many industry branches is also sometimes in nuclear technology. It is preferred that this material is used in many industrial fields because it is light and it can be given properties desired by alloying. Aerospace sector is considered as one of the most used sectors of aluminum alloys. In addition, aluminum has become a frequently used material in our daily lives also. However, it can be used in advanced technologies such as nuclear technology he others. Therefore, it is aimed to evaluate the situation in which aluminum alloys, which are routinely used in the industry, are used in nuclear technology and nuclear applications. Cs-137 gamma radioisotope source was used as a gamma radiation source in this study. The use of this gamma source is due to the use of a monochromatic gamma source and having long half-life. Therefore, it is thought to be more appropriate to evaluate it with a single energetic gamma source that could be described as medium energized. Working aluminum alloys are the most commonly used alloys from commercially used aluminum alloys. In this context, it is preferred to use alloys of 3xxx, 5xxx, 6xxx and 7xxx which are important and important ones of aluminum alloys in experiments. Working commercial use aluminum materials; 1050, 3003, 5005, 6063, 7072, 8006 aluminum materials. Since 1xxx series (except impurity elements) are unalloyed aluminum, it is thought that this series alloy can be used as reference alloy by working with this series. The realized experiments were carried out with an experimental setup which was constructed in accordance with the transmission technique geometry. Collimator and armor materials were used in the experiment to reduce the scattering effect. Thus, attenuation coefficients have been determined with the assumption that there is no scattering effect. Experiments with the Cs-137 gamma radioisotope source showed that the attenuation curves plotted on the basis of the experimental results obtained with commercially available commercial aluminum materials gave relatively similar results. The radiation attenuation curves plotted with the results obtained for the Cs-137 gamma radioisotope source; when examined, it was seen that 1050 pure aluminum material gave a very different result than the others. It is seen that the attenuation curves for the other doped aluminum alloy materials are very close to each other. It has been observed that the gamma radiation attenuation effect is better in commercially doped aluminum materials outside 1050. This is in line with expectations, suggesting that doping elements such as magnesium, manganese, zinc, silicon and iron, which are doped with 0.5% or more of aluminum, are effective in attenuating the radiation. Examination of the experimental results for the working aluminum materials is also aimed at in the scope of this Master's thesis. In this context, XCOM Computer program which is preferred with international reliability is used. In this context, the mass absorption coefficients are first calculated from the empirical studies and then theoretically calculated by the XCOM computer program. It has been found that the results obtained by comparative evaluations of experimental and theoretical mass absorption coefficients are very close to each other. It has been found that the difference between the experimental and theoretical mass absorption coefficients is less than 6%. If the 1050 series is not aluminum, this difference is less than 2,5%. In this context, it can be said that the results achieved with our experiments are reliable. Also, half-thickness values and tenth thickness values were determined for the aluminum alloys studied. For aluminum alloys other than the 1050 unadulterated material, very close half-thickness values and tenth thickness values were obtained. However, it has been found that the half-thickness and the tenth thickness values of 1050 material are considerably higher than other aluminum alloys. This result is in fiting line with the previous results and is in line with expectations. Studies have shown that doping of elements with high atomic number, which are doped with alumina, is important for attenuating gamma radiation. This is due to the fact that the electromagnetic radiation of the entrant is related to the interaction phenomena with matter and is important for gamma shielding of elements with high atomic number. It can be summirixed that, with this study of MSc thesis, the behaviors of 0.662 MeV energetic gamma radiation (Cs-137) in the case of commercial use of aluminum materials in nuclear technology have been observed with experiments and the experimental results were tested with XCOM Computer program and it has been seen that compatible results can be achieved