Safety Simulation of Therapeutic I-131 Capsule Using GEANT4

GEANT4를 이용한 치료용 I-131 캡슐의 안정성 시뮬레이션

  • Jeong, Yeong-Hwan (Department of Nuclear Medicine, Chonbuk National University Hospital) ;
  • Kim, Byung-Cheol (Department of Nuclear Medicine, Chonbuk National University Hospital) ;
  • Sim, Cheol-Min (Department of Nuclear Medicine, Chonbuk National University Hospital) ;
  • Seo, Han-Kyung (Department of Nuclear Medicine, Chonbuk National University Hospital) ;
  • Gwon, Yong-Ju (Department of Nuclear Medicine, Chonbuk National University Hospital) ;
  • Han, Dong-Hyun (Department of Radiotechnology, Seohae College)
  • 정영환 (전북대학교병원 핵의학과) ;
  • 김병철 (전북대학교병원 핵의학과) ;
  • 심철민 (전북대학교병원 핵의학과) ;
  • 서한경 (전북대학교병원 핵의학과) ;
  • 권용주 (전북대학교병원 핵의학과) ;
  • 한동현 (서해대학교 방사선과)
  • Received : 2014.09.19
  • Accepted : 2014.10.21
  • Published : 2014.11.08

Abstract

Purpose Iodine (I-131) is one of the most widely used radioactive isotopes for therapeutic in the field of nuclear medicine. Therapeutic I-131 capsule is made out of lead to shield high energy radiation. Accurate dosimetry is necessarily required to perform safe and effective work for relative workers. The Monte Carlo method is known as a method to predict the absorbed dose distribution most accurately in radiation therapy and many researchers constantly attempt to apply this method to the dose calculation of radiotherapy recently. This paper aims to calculate distance dependent and activity dependent therapeutic I-131 capsule using GEANT4. Materials and Methods Therapeutic capsules was implemented on the basis of the design drawings. The simulated dose was determined by generating of gamma rays of energy to more than 364 keV. The simulated dose from the capsule at the distance of 10 cm and 100 cm was measured and calculated in the model of water phantom. The simulated dose were separately calculated for each position of each detector. Results According to the domestic regulation on radiation safety, the dose at 10 cm and 100 cm away from the surface of therapeutic I-131 capsule should not exceed 2.0 mSv/h and 0.02 mSv/h, respectively. The simulated doses turned out to be less than the limit, satisfying the domestic regulation. Conclusion These simulation results may serve as useful data in the prediction of hands dose absorbed by I-131 capsule handling. GEANT4 is considered that it will be effectively used in order to check the radiation dose.

국내 갑상선암 환자의 발병률이 증가함에 따라 방사성요오드 치료가 필요한 환자가 증가하고 있다. 방사성 요오드 치료에 이용되고 있는 캡슐용기들 중 1.1 GBq과 5.5 GBq의 국산제품에 설계도면을 바탕으로 차폐체를 구현한 후 366 keV 이상에 감마선들에 대하여 캡슐용기의 방사선 누설선량을 GEANT4 전사모사를 이용하여 평가하였다. 치료용 I-131 캡슐용기 누설선량을 측정하기 위해 각각의 용기에 대하여 용기 표면에서 10 cm 거리 및 100 cm 거리에서의 누설선량을 측정하였다. 용기표면에서 10 cm 거리와 100 cm 거리에서의 누설선량 측정은 방사형으로 발생되는 방사선을 위치별로 측정하기 위해 $10{\times}10{\times}10cm^3$ 부피의 정육면체 형태의 물 팬텀(phantom)을 상부, 상부측면, 측면, 하부측면, 하부 다섯 방향에 설치하여 누설선량을 계산하였다. 용기별로 5개 방향에서 용기표면으로 부터 10 cm, 100 cm 거리에서 전산모사를 수행한 결과 법적 허용기준인 10 cm 거리에서 2.0 mSv/h, 100 cm 거리에서 0.02 mSv/h 이하의 선량 규정과 비교하였을 때 법적기준치보다 현저히 낮은 누설선량이 방출되는 것을 확인하였다.

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