医療用直線加速器使用室迷路からの漏洩中性子の遮蔽について

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Tow different experiments were conducted on shielding against neutron leakage from the maze of a medical linear accelerator room. One experiment was performed by placing neutron shielding materials made from boron carbide (B_4C) and polyethylene (manufactured by Tore Co., Ltd.) inside the entrance door, and the other by placing Lucite boards at the mouth of the maze. From the first experiment, the following facts were obtained. 1. The materials were mainly effective for thermal neutron shielding and the experimental values for thermal neutrons agreed well with the calculated results which considered only thermal neutron absorption in ^<10>B. 2. Tenth-value thickness of the materials was about 0.8kg/m^2 in B_4C thickness for thermal neutrons. 3. When materials were placed inside the entrance door to the maze, the dose equivalent for the capture gamma-rays in vicinity of the door decreased very effectively. Form the second experiment, the following became clear. 1. Tenth-value thickness of Lucite for a neutron dose equivalent depended on the position of the neutron source (Linac head) in the treatment room. The value was 7.5 cm nearest the source position and 5.5 cm farthest from the source position. 2. Dose equivalent transmission curve through a Lucite slab shield was nearly exponential within the limits of this experiment. A plan for leakage neutron shielding was made on the basis of above experimental results.
公益社団法人日本放射線技術学会の論文
1984-07-01

医療用直線加速器使用室迷路からの漏洩中性子の遮蔽について

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