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Original Article

Korean Journal of Medical Physics 2004; 15(4): 210-214

Published online December 25, 2004

Copyright © Korean Society of Medical Physics.

Shielding Calculations of Accelerator Facility for Medical Isotope Production using MCNPX Code

MCNPX 코드를 이용한 의료용 방사성동위원소 생산을 위한 가속기 시설의 방사선차폐 및 선량 계산

Kyu-Seok Seo, and Chan-Hyeong Kim

서규석·김찬형

Department of Nuclear Engineering, Hanyang University

한양대학교 원자력공학과

Abstract

Since production of radioactive isotope for using PET, a lot of neutrons were produced. The produced neutrons were mainly shielded by concrete facility. Secondary photons are generated and emitted from the concrete shielding wall of the PET cyclotron since the proton-generated neutrons are thermalized and absorbed in the concrete wall and emit secondary radiations, i.e., photons. This study calculated neutron dose and photon dose at outside of the accelerator facility using MCNPX code. As results of the calculation, total dose were calculated less than limited dose by law.

KeywordsAccelator facility, Shielding calculation, MCNPX code

Korean Society of Medical Physics

Vol.35 No.3
September 2024

pISSN 2508-4445
eISSN 2508-4453
Formerly ISSN 1226-5829

Frequency: Quarterly

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