Journal of Radiation Industry (방사선산업학회지)

Korean Society of Radiation Industry (한국방사선산업학회)
권호 표지

Calculation of Effective Half-life of Gamma Emission Radionuclide using Bio-kinetic Model

생체역동학 모델을 이용한 감마선 방출 핵종의 유효반감기 계산

  • 이상경 (고려대학교 바이오융합공학과) ;
  • 정규환 (한국원자력안전기술원) ;
  • 이지연 (한국원자력안전기술원) ;
  • 김봉기 (과학기술연합대학원대학교) ;
  • 김정민 (고려대학교 보건환경융합과학부)
  • Received : 2018.08.10
  • Accepted : 2018.10.10
  • Published : 2018.12.31

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Abstract

Patients administered radioisotope for medical purposes are regulated by each country to quarantine them until their body's radioactivity contents decrease below release criteria. To predict the quarantine period and provide it to medical staffs and patients, it is necessary to approach the assessment of the exposure dose of persons due to patients in a realistic manner. For this purpose, a whole-body effective half-life should be applied to the dose assessment equation instead of the physical half-life. In this study, we constructed a bio-kinetic model for each nuclear species based on the ICRP publication to obtain a whole-body effective half-life of 10 unsealed gamma-ray emitting nuclei from the notification of Nuclear Safety and Security Commission, and calculated the effective half-life mathematically by simulating the distribution of the radioisotope administered in the whole body as well as each organ scale. The whole-body effective half-life of $^{198}Au$, $^{67}Ga$, $^{123}I$, $^{111}In$, $^{186}Re$, $^{99m}Tc$, and $^{201}TI$ were 1,93, 2.57, 0.295, 2.805, 1.561, 0.245, and 2.397 days respectively. However, it was found to be undesirable to offer a single value of the effective half-life of $^{125}I$, $^{131}I$, and $^{169}Yb$ because the changes in the effective half-life show no linearity. A bio-kinetic model created for the internal exposure assessment has been shown to be possible to calculate the effective half-life of radioisotopes administered in the patient's body, but subsequent studies of radiolabeled compounds are required as well.

Keywords

Acknowledgement

Supported by : Nuclear Safety and Security Commission (NSSC)

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