몬테칼로 시뮬레이션을 활용한 양성자가속기 단기사용 시 구성품의 방사화 평가

• Published in: 방사선기술과학 Vol. 43; no. 5; pp. 389 - 395
• Main Authors: 배상일(Sang-Il Bae), 김정훈(Jung-Hoon Kim)
• Format: Journal Article
• Language: Korean
• Published: 대한방사선과학회(구 대한방사선기술학회) 30.10.2020; KOREAN SOCIETY OF RADIOLOGICAL TECHNOLOGY; 대한방사선과학회
• Subjects: 방사선과학; 몬테칼로 시뮬레이션; 양성자가속기; 방사화 생성물; Proton Accelerator; Activation product; Bragg peak; 중성자; MCNP; Neutron; 브래그 피크
• ISSN: 2288-3509; 2384-1168

The evaluation of radioactivated components of heavy-ion accelerator facilities affects the safety of radiation management and the exposure dose for workers. and this is an important issue when predicting the disposal cost of waste during maintenance and dismantling of accelerator facilities. In this study, the FLUKA code was used to simulate the proton treatment device nozzle and classify the radio-nuclides and total radioactivity generated by each component over a short period of time. The source term was evaluated using NIST reference beam data, and the neutron flux generated for each component was calculated using the evaluated beam data. Radioactive isotopes caused by generated neutrons were compared and evaluated using nuclide information from the International Radiation Protection Association and the Korea Radioisotope association. Most of the nuclides produced form of beta rays and electron capture, and short-lived nuclides dominated. However, In the case of 54Mn, which is a radioactive product of iron, the effect of gamma rays should be considered. In the case of tritium generated from a material with a low atomic number, it is considered that handling care should be taken due to its long half-life.