Tracz G, Dabkowski L, Dworak D, Pytel K, Woźnicka U
The Henryk Niewodniczański Institute of Nuclear Physics of the Polish Academy of Sciences, ul. Radzikowskiego 152, 31-342 Kraków, Poland.
Radiat Prot Dosimetry. 2004;110(1-4):827-31. doi: 10.1093/rpd/nch145.
The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for the boron neutron capture therapy (BNCT) facility to be located at the Polish research nuclear reactor MARIA at Swierk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised to moderate fission neutrons to epithermal energies and to remove both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both high epithermal neutron flux and suitably low level of beam contamination. Photons originating from the reactor core are almost eliminated what is the exceptional advantage of the proposed design. It yields one order of magnitude lower gamma radiation dose than the maximum allowed dose in such a type of therapeutic facility. The MCNP code has been used for the computations.
本文介绍了为位于斯韦尔克的波兰研究性核反应堆玛丽亚的硼中子俘获治疗(BNCT)设施设计的基于裂变转换器的超热中子源的数值模拟结果。由于反应堆特殊的几何环境,提出了裂变转换器的独特设计。对过滤器/慢化剂装置进行了优化,以将裂变中子慢化到超热能,并从治疗束中去除快中子和光子。所选的过滤器/慢化剂设置确保了高超热中子通量和适当低水平的束污染。源自反应堆堆芯的光子几乎被消除,这是所提出设计的独特优势。它产生的伽马辐射剂量比这种类型治疗设施中允许的最大剂量低一个数量级。计算使用了MCNP代码。