Optimization study for BNCT facility based on a DT neutron generator
Optimization study for BNCT facility based on a DT neutron generator
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DOI：
10.7508/ijrr.2015.01.002
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发表时间：
2015-01
影响因子：
--
通讯作者：
J. Fantidis;A. Antoniadis
中科院分区：
文献类型：
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作者：
J. Fantidis;A. Antoniadis
背景资料：介绍了一种基于DT中子发生器的硼中子俘获治疗（BNCT）装置，其最终目标是寻找一种潜在的、替代的、解决方案，以研究基于核反应堆的BNCT治疗装置。材料与方法：采用MCNP 4 B蒙特卡罗程序，对不同构型的光束整形组件（BSA）进行了模拟。选用铅作为反射体材料，CF2、D2 O、Fluental、PbF 4、PbF 2、BiF 3、BiF 5、MgF 2、Al 2 O3、AlF 3、TiF 3、BeD 2、CaF 2和7 LiF作为光谱屏蔽体。为了提高束流质量，用镍-60、铁和钛合金（Ti-6Al-14 V）模拟快中子过滤器，用铅和铋模拟γ过滤器。结果如下：用MCNP 4 B蒙特卡罗程序进行了大量计算，结果表明：7 LiF + D2 O + TiF 3是最佳慢化剂设计。使用三种不同的材料来进一步减少快中子、热中子和伽马射线是必要的。60
Background : A Boron Neutron Capture Therapy (BNCT) facility, based on a DT neutron generator, with the final goal to find out a potenal, alternave, soluon to exisng BNCT treatment facilies which a re based on nuclear reactors is examined. Materials and Method s: With the aim of the MCNP4B Monte Carlo code different beam-shaping assembly (BSA) configuraons were considered. Lead was selected as reflector material while CF 2, D 2O, Fluental, PbF 4, PbF 2, BiF 3, BiF 5, MgF 2, Al 2O3, AlF 3, TiF 3, BeD 2, CaF 2 and 7 LiF were examined as spectrum shi3ers. In order to improve t he quality of the beam �tanium, nickel-60, iron andtanium alloy (Ti 6Al 14 V) were simulated as fast neutrons filters while lead and bismuth were considered as gamma filters. Results: An extensive set of calculaons performed with MCNP4B Monte Carlo code have shown that the combinaon of 7 LiF which accommodates a conic part made of D 2O, then followed by a TiF 3 layer is the opmum moderator design. The use of three different materials for further reducon of fast neutrons, thermal neutrons and gamma rays is necessary. 60