Some medical compact cyclotrons have selfshielding to reduce neutron fluxes. Thermal neutron fluxes in an 18-MeV unshielded cyclotron room and in a 16.5- MeV self-shielded cyclotron room were evaluated. In addition, the radioactivities in concrete and metals due to thermal neutrons in the cyclotron rooms for 30 years were calculated of operation such that the sum of the ratio of the nuclide concentration to the nuclide clearance level was equal to 1. The thermal neutron flux from the unshielded cyclotron was approximately 10 2 cm-2 s-1, whereas that from the self-shielded cyclotron was approximately 102 cm-2 s-1. The thermal neutron fluxes for concrete, stainless steel, vessel steel, and aluminum that reached their clearance levels were 9.80 × 104, 2.17 × 103, 1.87 × 104, and 2.41 × 10 5 cm-2 s-1, respectively. The specific activities in the cyclotron room were found to be sufficiently below the clearance level when the self-shield was employed.
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