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

• Published in: Applied radiation and isotopes Vol. 69; no. 12; pp. 1632 - 1634
• Main Authors: Kandiev, Ya, Kashaeva, E., Malyshkin, G., Bayanov, B., Taskaev, S.
• Format: Journal Article
• Language: English
• Published: England Elsevier Ltd 01-12-2011
• Subjects: Accelerator; Epithermal neutron source; Monte Carlo method; PRIZMA code; Monte Carlo method; PRIZMA code; Epithermal neutron source; Accelerator
• ISSN: 0969-8043; 1872-9800
• DOI: 10.1016/j.apradiso.2011.02.052

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.