Gamma Spectroscopy Characterization in Situ for Radioactive Waste Barrels Contaminated with ¹³⁷Cs

In order to determine the final decision for the management of radioactive waste for temporary or permanent storage, the quantitative and qualitative analysis of the waste of radioactive waste is required so as to avoid the use of expensive scanning gamma system and the consumption of time and money. Therefore, we used the relative comparative method by creating a standard source in the form of a container barrel of a contaminated soil with cesium radioisotope with known ratios to be similar to the models of barrel of radioactive waste in terms of physical and chemical properties. The relationship between the specific radioactivity of the radioactive waste in the barrel and the dose represented by using the five following equations of the portable gamma ray detectors: y=16893x+3371.7, y=13332x+898.06, y=25189x+2313.9, y=24145x+2150.8, y=21683x+3149.4, for Inspector, Identifinder, Ludlum, Inspector1000 and HPGe detectors respectively.