Comparing the effects of various (p,xn) radionuclide production routes on induced radioactivity in the concrete walls of a cyclotron vault.

In sum, 11 (p,xn) related nuclear reactions with 9 target materials, namely 18O(p,n)18F, 15N(p,n)15O, 68Zn(p,n)68Ga, 68Zn(p,2n)67Ga, 69Ga(p,2n)68Ge, 89Y(p,n)89Zr, 100Mo(p,pn)99Mo, 100Mo(p,2n)99mTc, 112Cd(p,2n)111In, 124Xe(p,2n)123Cs and 203Tl(p,3n)201Pb, are involved in the operation of 13 radionuclide-production cyclotrons in Taiwan. The secondary neutrons accompanying these production routes could induce varying degrees of material activation in the cyclotron facility. Accordingly, this study compared the effects of various (p,xn) production routes on the neutron-induced long-lived radioactivity in the concrete walls of a hypothetical cyclotron vault. In addition, an activation-reduction approach involving the addition of a layer of neutron-absorbing material to the surface of inner concrete walls was evaluated.

Shielding analysis of the proton therapy facility at China Medical University Hospital: comparison of a simplified approach with Monte Carlo simulations.

This study comprehensively compared two approaches for analyzing the shielding design of the proton therapy facility at China Medical University Hospital. The first approach essentially involved two approximate models: one for estimating the transmitted radiation through thick shields, and one for estimating radiation streaming at locations near a maze entrance. The second approach relied on Monte Carlo simulations for predicting the radiation field in a complex environment. A total of 22 beam loss scenarios were considered, and dose rates at 32 locations around the facility were estimated using the two approaches. The comparison results demonstrated that the simplified approach proposed in this study can yield fairly accurate or conservative estimates for quickly performing shielding design or dose assessment in a real-world proton therapy facility.