[논문]Radiation safety analysis for the A-BNCT facility in Korea

Lee, Eunjoong; Lee, Cheol-Woo; Cho, Gyuseong

doi:10.1016/j.apradiso.2018.09.022

Radiation safety analysis for the A-BNCT facility in Korea

Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry, and medicine, v.142, 2018년, pp.92 - 103

Lee, Eunjoong (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon 305-701, Republic of Korea) , Lee, Cheol-Woo (Nuclear Data Center, Korea Atomic Energy Research Institute, Daejeon 305-353, Republic of Korea) , Cho, Gyuseong (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon 305-701, Republic of Korea)

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Abstract A Proton Accelerator based Boron Neutron Capture Therapy (A-BNCT) facility is under development in Korea. Neutron beams for treatment are produced from a beryllium (Be) target and an 8 mA, 10 MeV proton beam. The purpose of the research is a radiation shielding analysis and an activation analysis for the facility design satisfying the radiation safety requirements as well as obtaining an operating license for the radiation facility according to a domestic nuclear commissioning procedure. The radiation shielding analysis was performed using the MCNPX computational particle transport code. The radiation source terms in the facility were evaluated and utilized in the shielding calculations. The minimum concrete thickness satisfying the designated dose rate of 5 μSv/h for the worker's area and 0.25 μSv/h for the public area were estimated and applied to the design. For an assessment of the radiation safety inside the facility, the dose rates were evaluated at several positions, such as behind the shielding door, around the primary barriers near the radiation sources, and in the penetrations of the ducts. The dose rate distribution was mapped for verification of the radiation safety for the entire facility. An activation analysis was carried out for the concrete walls, air, target assembly, beryllium target, and cooling water using FISPACT-2010 code. Concentrations of the activation products and dose rate induced by the radionuclides after shutdown were evaluated for the purpose of safe operation of the facility. The results were reviewed with the radiation safety regulations in Korea. As a result, it was proved that the final facility design satisfies the safety requirements. Highlights A Proton Accelerator based Boron Neutron Capture Therapy (A-BNCT) facility is under development in Korea. Radiation shielding analysis was carried out using MCNPX code The facility design was determined satisfying designated dose limit Neutron activation analysis was performed with MCNPX and FISPACT code The concentration of radionuclides were reviewed with the radiation safety regulations.

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Radiation safety analysis for the A-BNCT facility in Korea

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Radiation safety analysis for the A-BNCT facility in Korea

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