Detecting strontium-89 removable contamination using a sodium iodide well counter.
| Autor: | Hackett MT; Radiation Safety Office, Department of Veterans Affairs Medical Center, Lexington, Kentucky 40511-1093, USA., Coupal JJ, Perdikaris N |
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| Jazyk: | angličtina |
| Zdroj: | Journal of nuclear medicine technology [J Nucl Med Technol] 1997 Sep; Vol. 25 (3), pp. 195-200. |
| Abstrakt: | Unlabelled: Monitoring for 89Sr removable contamination is required for incoming DOT-labeled packages and work areas containing radioactivity. However, few nuclear medicine departments are equipped for liquid scintillation counting, which is the preferred method for detecting beta emitters. We investigated using a sodium iodide well counter to detect 89Sr through its bremsstrahlung photon production. Methods: We used a manufacturer's 89Sr-chloride solution of known concentration and tested various parameters: type of tube, access of tube contents to air, volume of sample, type of wipe material and counting geometry. Liquid scintillation samples also were obtained. Results: Initial counting efficiencies were 0.10-0.14 cpm/dpm for small volume (10-microliter) samples. The various parameters tested had either positive or negative effects on the system's efficiency to detect 89Sr. One set of samples, counted over time, demonstrated a calculated mean half-life of 50.8 days, which is similar to the 89Sr reported half-life of 50.5 days. Liquid scintillation samples demonstrated efficiencies of almost 1.0 cpm/dpm and a calculated mean half-life of 50.8 days, both as expected. Conclusion: This study demonstrates that 89Sr removable contamination can be detected sensitively using a sodium iodide well counter, but special considerations must be made when determining the system's counting efficiency. |
| Databáze: | MEDLINE |
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