[Leakage neutrons and X-rays in a therapeutic microtron facility]

Measurements of dose equivalent rate distribution in a medical microtron facility were done for neutrons and X-rays originated from 14 MV or 8 MV X-ray irradiation by the microtron. Measured data are described with empirical formulas for convenience of quantitative reconstruction of the data. A formula consisting of a simple power function agrees well with measured data except for thermal neutrons, and is understood to describe the dose rate separating into the scattered and unscattered components in the case of the point source. The thermal neutron distribution in the maze is described with another formula of an exponential function. A discrepancy was observed between the X-ray distribution in the maze from 14 MV X-ray irradiation and that from 8 MV irradiation. This is estimated to be caused by a contribution of capture gamma-rays increasingly emitted in the case of 14 MV X-ray irradiation.