SPECT and planar γ-camera imaging for volume and activity determination of I131 sources applying threshold technique

• Κύριος συγγραφέας: Μπαρμπαγιαννίδης, Προκόπιος
• Άλλοι συγγραφείς: Κάππας, Κωνσταντίνος
• Μορφή: Thesis
• Γλώσσα: English
• Έκδοση: 2009
• Θέματα: Threshold technique; SPECT; I-131; Τεχνική κατωφλίου; Ποσοτικοποίηση; 616.075 75

Absolute quantification of the 3D distribution of a radionuclide within a patient has been one of the greatest challenges of nuclear medicine. This is due to the fact that nuclear medicine images are degraded by several factors, which limit the quantitative ability of this modality. Quantitative SPECT has wide applications in many areas in nuclear medicine from radiation dosimetry calculations to clinical applications. It has use in image analysis studies to extract information about areas, volumes, and/or amounts of radioactivity in specific regions of interest. The information that derived from these studies is then applied to estimate radiation dosimetry, volumes or to aid in clinical diagnoses. Absolute quantitation means precise and accurate measurements of volume and the amount of radioactivity in a specific region of interest. For absolute quantitation of volume the measurements can be expressed in cubic centimetres, for radioactivity in μCi or Bq. Quantitation of organ volumes using planar imaging technique is a procedure often performed in nuclear medicine but face difficulties due to structure containing radioactivity, which overlie or underlie the organ of interest. SPECT overcomes these difficulties since it is able to separate these structures in the reconstructed images, which have higher contrast than planar images. In the theoretical part of this work, there is a description of the operation and the characteristics of a gamma camera system. Following that, there is a mention to the quality control procedures of the system both for planar and SPECT techniques. Also, there is an extended discussion of the factors that affect to the image quantitation and the corrections that must be applied in order to achieve better volume and activity estimation. At the end of the theoretical part, there is a presentation of procedure for volume and activity quantitation on I-131 sources using threshold technique. In the practical part, there is a study on volume and activity quantitation for I-131 sources with volumes 0.5,1,5,8,10,20 and activities from 300 to 529 μCi using threshold technique. The practical part of this work was performed in the department of Nuclear Medicine of the “THEAGENION” Cancer Institute of Thessaloniki (Greece), with association with the department of Medical Physics.