Jove
Visualize
Contact Us
JoVE
x logofacebook logolinkedin logoyoutube logo
ABOUT JoVE
OverviewLeadershipBlogJoVE Help Center
AUTHORS
Publishing ProcessEditorial BoardScope & PoliciesPeer ReviewFAQSubmit
LIBRARIANS
TestimonialsSubscriptionsAccessResourcesLibrary Advisory BoardFAQ
RESEARCH
JoVE JournalMethods CollectionsJoVE Encyclopedia of ExperimentsArchive
EDUCATION
JoVE CoreJoVE BusinessJoVE Science EducationJoVE Lab ManualFaculty Resource CenterFaculty Site
Terms & Conditions of Use
Privacy Policy
Policies

Related Experiment Videos

Detecting strontium-89 removable contamination using a sodium iodide well counter

M T Hackett1, J J Coupal, N Perdikaris

  • 1Radiation Safety Office, Department of Veterans Affairs Medical Center, Lexington, Kentucky 40511-1093, USA.

Journal of Nuclear Medicine Technology
|September 18, 1997
PubMed
Summary

A sodium iodide well counter can detect Strontium-89 (89Sr) contamination, offering an alternative to liquid scintillation counting. Careful calibration is needed to determine the system's counting efficiency for accurate monitoring.

Related Concept Videos

You might also read

Related Articles

Articles linked to this work by shared authors, journal, and citation graph.

Sort by
Same author

Brain SPECT artifacts in patients having metallic cranioplasty.

Journal of nuclear medicine technology·2002
Same author

Lymphoscintigraphy of melanoma: lymphatic channel activity guides localization of sentinel lymph nodes, and gamma camera imaging/counting confirms presence of radiotracer in excised nodes.

Annals of nuclear medicine·2001
Same author

A simple solution to prevent the loss of radioactive spot markers.

Journal of nuclear medicine technology·2000
Same author

Radioactive contamination of packing materials from a xenon-133 shipment.

Journal of nuclear medicine technology·2000
Same author

Myositis ossificans demonstrated by positive gallium-67 and technetium-99m-HMDP bone imaging but negative technetium-99m-MIBI imaging.

Journal of nuclear medicine technology·1999
Same author

Tc-99m MIBI thoracic SPECT for the detection of intrathoracic tumor masses.

Clinical nuclear medicine·1998

Area of Science:

  • Nuclear medicine
  • Radiological monitoring
  • Radiation detection

Background:

  • Monitoring for Strontium-89 (89Sr) removable contamination is crucial for radioactive materials.
  • Liquid scintillation counting is the preferred method but not widely available in nuclear medicine departments.
  • Alternative detection methods for beta emitters like 89Sr are needed.

Purpose of the Study:

  • To investigate the use of a sodium iodide well counter for detecting 89Sr contamination.
  • To evaluate the feasibility of using bremsstrahlung photon production for 89Sr detection.
  • To compare the performance of a sodium iodide well counter with liquid scintillation counting.

Main Methods:

  • Tested 89Sr-chloride solutions of known concentration.

Related Experiment Videos

  • Evaluated parameters including sample volume, tube type, air access, wipe material, and counting geometry.
  • Obtained liquid scintillation samples for comparison.

    • Main Results:

    • Initial counting efficiencies for the well counter were 0.10-0.14 cpm/dpm for small samples.
    • Various tested parameters affected the system's detection efficiency.
    • Calculated half-life of 50.8 days closely matched the known 50.5-day half-life of 89Sr.
    • Liquid scintillation samples showed expected efficiencies (approx. 1.0 cpm/dpm) and half-life.

    Conclusions:

    • Sodium iodide well counters can sensitively detect 89Sr removable contamination.
    • Special considerations are necessary for determining counting efficiency with this method.
    • This offers a viable alternative for departments without liquid scintillation capabilities.