Research Article, J Nucl Ene Sci Power Generat Technol Vol: 5 Issue: 4
Recycling of a Disused 137Cs Sealed source
|Lina Al Attar1, Alan Dyer2*, Mohammad Al-Oudat1, Bassam Safia1 and Basem Abdul Ghani1|
|1Department of Protection and Safety, Atomic Energy Commission of Syria, Damascus, Syria|
|2Institute of Materials Science, University of Salford, Salford, UK|
|Corresponding author : Alan Dyer
Institute of Materials Science, University of Salford, Salford, M5 4WT, UK
|Received: April 21, 2016 Accepted: July 19, 2016 Published: July 23, 2016|
|Citation: Attar LA, Dyer A, Al-Oudat M, Safia B, Ghani BA (2016) Recycling of a Disused 137Cs Sealed source. J Nucl Ene Sci Power Generat Technol 5:4. doi:10.4172/2325-9809.1000160|
Recycling of disused sealed radioactive sources (DSRS) is one of the milestones of radioactive waste management strategy that prompts the minimisation of the radiological hazard to human health and the environment. In this respect this study spotlights recovering and purification of 137Cs as a solution (with a radioactivity of 191.5 ± 3.9 MBq) from an old disused source. The method was designed to fulfil the regulations and legislations of radiation protection giving exposure doses of the operating staff within the international permissible limits. Separation of the chemical impurities was performed by hydroxide precipitation based on pH values and solubility constants. X-ray fluorescence analysis illustrated a removal efficiency of 99% for iron and chromium, whereas the concentration of nickel and manganese decreased to 80 and 7 mg L-1, respectively, in the purified 137Cs solution. The radiochemical recovery of the purification process was determined using gamma-spectroscopy and found to be 94.4%.
The purified 137Cs solution was then used to prepare a gel-source with 20 mL cylindrical geometry. Calibration was carried out at a secondary standard laboratory “National Radioactive Measurement Laboratory” (NRML) that is traceable to the primary standard “National Physics Laboratory” in the UK (NPL), giving an activity of 10.59 MBq with relative uncertainty of 0.4-0.5%. The preparation procedure could be considered as an original, facile, feasible and cost effective method that implies beneficial reuse of a DSRS in terms of volume minimization of radioactive wastes.