Design of beam shaping assembly for boron neutron capture therapy based on D-T neutron source

ZHU Yinan; LIN Zuokang; LU Linyuan; YU Haiyan; CHEN Jingen; XIE Leidong

doi:10.11889/j.0253-3219.2022.hjs.45.010202

He jishu (Jan 2022)

Design of beam shaping assembly for boron neutron capture therapy based on D-T neutron source

ZHU Yinan,
LIN Zuokang,
LU Linyuan,
YU Haiyan,
CHEN Jingen,
XIE Leidong

Affiliations

ZHU Yinan: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
LIN Zuokang: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
LU Linyuan: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
YU Haiyan: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
CHEN Jingen: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
XIE Leidong: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China

DOI: https://doi.org/10.11889/j.0253-3219.2022.hjs.45.010202
Journal volume & issue: Vol. 45, no. 1
pp. 010202 – 010202

Abstract

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BackgroundBoron neutron capture therapy (BNCT) is a promising treatment for cancer. In recent years, D-T neutron source has shown great potential as a suitable neutron source for BNCT. However, the neutron energy produced by a D-T neutron source is 14.1 MeV, which cannot be straightforwardly used in a BNCT, so beam shaping is necessary.PurposeThis study aims to design beam shaping assembly (BSA) to make the neutron beam of D-T neutron source suitable for BNCT.MethodsThe Monte Carlo simulation program MCNP5 was employed to design the corresponding BSA for D-T neutron source. The advantages of using natural uranium as neutron multiplicative layer was firstly verified by simulation. Then, the moderating layer was simulated together the supplementary moderating layer, reflective layer, shielding layer and thermal neutron absorption layer using different materials and thickness to obtain optimal configuration of these materials.ResultsSimulation results show that an ideal therapeutic neutron beam is obtained by using a 14 cm radius natural uranium as neutron multiplicative, 50 cm thick BiF3 and 10 cm thick TiF3 as a double-moderating layer, a 17 cm thick AlF3 as a supplementary moderator, a 0.2 mm thick Cd as a thermal neutron absorbing layer, a 3.5 cm thick Pb as a γ shielding layer and a 10 cm thick Pb as a reflecting layer. Combination of these materials is suggested to optimize and design as the neutron BSA.ConclusionsThe air outlet parameters of output neutron beam using BSA designed in this study can well meet the recommended values of the International Atomic Energy Agency (IAEA).

Published in He jishu

ISSN: 0253-3219 (Print)
Publisher: Science Press
Country of publisher: China
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: https://www.hjs.sinap.ac.cn/

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