Radiological characterization of a uranium glass collectible by gamma spectrometry

The purpose of this work was the non-destructive characterization by gamma spectrometry of a collector's item in which uranium was used as a colouring agent. Such characterization was based on the calculation of the counting efficiency as a function of energy using the LabSOCS software from Canberra Industries. The activity concentrations obtained for the uranium isotopes were verified: i) from the measurement of two different positions of the test piece, ii) from the indirect calculation of the percentage by mass of U3O8 (wt%) and iii) from the ambient dose equivalent rate H*(10) using the MCNP code. The activity concentrations obtained for 238U (9031 ± 2919 Bq kg−1) and 235U (472 ± 23 Bq kg−1) led to the conclusion that it was natural uranium. The value of the rate of ambient dose equivalent H*(10) in contact was 390 nSv h−1, which corresponds to twice the natural background. The U3O8 content obtained was 0.213 ± 0.013%.