Feasibility of Simultaneous 152Eu and 154Eu radioisotope production from natural europium for gamma spectrometry calibration

In this study, the feasibility of producing two radioisotopes, 152 Eu and 154 Eu, through irradiation of natural europium was investigated using the MCNPX 2.6 code and MATLAB computational software. 152 Eu and 154 Eu radioisotopes are used as standard radioactive sources in industrial and research applications for the calibration of gamma radiation measuring systems. The sample was simulated in the B1 irradiation location of the Tehran Research Reactor core, at a point with the highest neutron flux (1.31 × 10 13 n/cm 2 s). To optimize reactor operation cycles and manage radioactive waste, the optimal cooling time was set to 12 days. The activity of the produced isotopes was examined and evaluated for a 7-day irradiation period and a 12-day cooling period. Results indicated that, in addition to 152 Eu, recognized as a calibration source in the industry, 154 Eu could also be introduced and utilized as an efficient and suitable option for gamma spectrometry system calibration. Furthermore, a reasonable difference was observed between the results of the two methods, indicating that MATLAB, for several decades its simplicity and speed in providing initial approximations, serves as a suitable option for preliminary assessments. However, for more precise evaluations and consideration of all details, the MCNPX code is a more appropriate solution. Therefore, it can be concluded that while MATLAB can provide quick initial estimates, the MCNPX code provides more accurate evaluations by calculating additional complexities. This insight allows researchers to choose the most appropriate computational tools based on the specific needs of their work.