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KMID : 1038720140250010008
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Progress in Medical Physics
2014 Volume.25 No. 1 p.8 ~ p.14
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Measurement and Estimation for the Clearance of Radioactive Waste Contaminated with Radioisotopes for Medical Application
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Kim Chang-Bum
Park Min-Seok
Kim Gi-Sub
Jung Hai-Jo
Jang Seong-Joo
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Abstract
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The amounts of radioactive wastes to be disposed in the medical institute have been increased due to development of radiation diagnosis and therapy rapidly. They are produced mostly by the very short lived radioisotopes such as 18F used in PET/CT, 99mTc, 123I, 125I and 201Tl, etc. IAEA proposed a criteria for the clearance level of waste which depends on the individual (10μSv/y) and collective dose (1 man-Sv/y), and concentration of each nuclide (IAEA Safety Series No 111-P-1.1, 1992 and IAEA RS-G-1.7, 2004). Radioactive wastes of 18F, 99mTc, 123I, 125I and 201TI in the several types of container like Marinelli beaker, vial and plastic, were collected to measure the concentration of the waste of each nuclide in accordance with IAEA criteria. The measurement method and procedure of determining specific activity of the wastes using gamma emitters like MCA, gamma counter and beta emitters were developed. For the efficiency calibration of the detectors, CRM (certified reference material) which has the same dimension and shape was provided by Korea Research Institute of Standards and Science (KRISS). Correction factor of the radioactivity decay was calculated based on the measurement results, and the consideration of mutual relation with theoretical equation. The result of this study will be proposed as ISO standard.
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KEYWORD
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Radioactive waste, Self disposal, Medical radioactive isotope, Specific radioactivity
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