The transport and radiological traces of natural and artificial radionuclides in the samples taken from the boron waste storage area of the Bandırma boron production facility have been investigated. Boron raw materials were supplied from Kirka (Turkey) and Emet (Turkey) quarries. Radiological dose values were examined in nine different samples. The samples coded A3, A10 and A11 represent waste derived from just the Emet deposit, whereas samples A4, A5, A6, A7, A8, and A9 were waste derived from both Kirka and Emet deposits. Natural and artificial radionuclide concentration levels of ²²⁶Ra, ²³²Th, ⁴⁰K, and ¹³⁷Cs in these wastes were determined using a high-purity germanium detector. The calculations showed that the activity concentration values for ²²⁶Ra, ²³²Th, ⁴⁰K, and ¹³⁷Cs were compatible with the waste analysis results in the literature. In this study, many parameters indicating radiological hazards have been calculated. In this study, the radiological risk assessment parameters for samples taken from the boron waste storage site were determined and compared with the world average values. The results obtained from the analyses showed that the best waste value belonged to sample A6 from the Kirka deposit in Turkey. In addition, due to environmental effects and the presence of other wastes (A11), the radiological hazard level was high in waste from the Emet deposit.