방사화 표적물질 운반용기 설계 연구
A Study on Design of Transport Container for Radio-activated Targets
0
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
KOMAC (Korea Multi-Purpose Accelerator Complex, KAERI) has been operating a100 MeV proton accelerator and is going to produce 68Ga isotope which is useful for diagnosis of cancer. So, it is necessary to develop a transport container for radio-activated targets. In this study, we carryout shielding analysis and structural analysis for the radio-activated target transport container usingsimulation programs. According to the Type A standard, the transport container includes an innercontainer and an overpack container. The main material of inner container is lead, and the shape iscylindrical with diameter of 152 mm, height of 142 mm and weight about 29 kg. It is planned to verify thepossibility of field application through production of the transport container prototype in the future.
Abstract
KOMAC (Korea Multi-Purpose Accelerator Complex, KAERI) has been operating a100 MeV proton accelerator and is going to produce 68Ga isotope which is useful for diagnosis of cancer. So, it is necessary to develop a transport container for radio-activated targets. In this study, we carryout shielding analysis and structural analysis for the radio-activated target transport container usingsimulation programs. According to the Type A standard, the transport container includes an innercontainer and an overpack container. The main material of inner container is lead, and the shape iscylindrical with diameter of 152 mm, height of 142 mm and weight about 29 kg. It is planned to verify thepossibility of field application through production of the transport container prototype in the future.
참고문헌 (5)
- Nuclear Safety And Security Commission, "Rules on technical standards of radiation safety control, etc", NSSC Regulation Article 29, ~ (2021)
- Nuclear Safety And Security Commission, "Regulation on Packaging or Transport of Radioactive Material, etc", NSSC Notification 2021-2, ~ (2021)
- Delacroix D, "Radionuclide and radiation protection data handbook", pp.64~65 (2002), Nuclear Technology Publishing
- 이상봉, "MCNP를 이용한 Zr-89 운반용기의 차폐적정성 평가", 방사선산업학회지, 12(3), pp.163~168 (2018), (사)한국방사선산업학회[DOI]
- 신승훈, "An Approach to the Localization of Technology for a Transport and Storage Container for Very Low-Level Radioactive Liquid Waste", Journal of Nuclear Fuel Cycle and Waste Technology, 20(1), pp.127~131 (2022), 한국방사성폐기물학회[DOI]