2011 Accelerators Article BSA designs Dosimetry ICNCT14 Physics

Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code

Applied Radiation and Isotopes, 2011

Authors:   Ya. Kandiev,E. Kashaeva,G. Malyshkin,B. Bayanov,S. Taskaev,
Journal: Applied Radiation and Isotopes
Abstract: At Budker Institute of Nuclear Physics, epithermal neutron source for neutron-capture therapy was built and neutron generation was realized. Source is based on tandem accelerator and uses near-threshold neutron generation from the reaction 7Li(p,n)7Be. The paper describes target optimization through the numerical simulation of proton, neutron and gamma transport by Monte Carlo method (PRIZMA code). It is shown that the near-threshold mode attractive due low activation provides high efficiency of the dose and acceptable therapeutic ratio and advantage depth.