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  • [Appl Radiat Isot.] Radiation safety analysis for the A-BNCT facility in Korea.

    KAIST / 이은중, 조규성*

  • 출처
    Appl Radiat Isot.
  • 등재일
    2018 Sep 19
  • 저널이슈번호
    142:92-103. doi: 10.1016/j.apradiso.2018.09.022. [Epub ahead of print]
  • 내용

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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.

     


    Author information

    Lee E1, Lee CW2, Cho G3.
    1
    Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon 305-701, Republic of Korea.
    2
    Nuclear Data Center, Korea Atomic Energy Research Institute, Daejeon 305-353, Republic of Korea.
    3
    Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon 305-701, Republic of Korea. Electronic address: gscho@kaist.ac.kr.

  • 키워드
    Activation analysis; Boron Neutron Capture Therapy; Monte Carlo simulation; Proton accelerator; Radiation shielding analysis
  • 편집위원

    본 논문은 Applied Radiation and Isotopes 저널에 개제된 논문으로 양성자 가속기 기반의 보론 중성자 포획 (A Proton Accelerator based Boron Neutron Capture Therapy, A-BNCT)치료실의 차폐계산이 수행되었음.
    BNCT 치료실의 차폐 계산으로 위해 MCNPX 2.7 버전이 사용되었으며 치료실 내부를 총 3개의 공간으로 분리한 뒤 각 공간에서의 선량률을 계산하였음. (실제 치료가 수행되는 High level radiation area, 방사선작업종사자들이 주로 사용하는 공간인 Radiation worker`s area, 그리고 일반인들이 사용하는 Public area로 나누었음)
    최종적으로 MCNPX를 통해 계산된 각 부분의 선량률은 ICRP-103에서 제시하는 선량 제한치를 기반으로 평가되었으며 이 수치를 통해 현재 한국에서 개발중인 A-BNCT 치료실의 외벽 두께가 계산되었음.

    2018-10-23 12:35:10

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