高额超热中子束流治疗孔道低浓化BNCT堆初步设计方案
Preliminary Design of LEU MNSR for BNCT with Excellent Epithermal Neutron Flux Treatment Beam
于涛 1钱金栋 1谢金森1
作者信息
- 1. 南华大学核科学技术学院,湖南衡阳,421001
- 折叠
摘要
根据硼中子俘获治疗( BNCT)中子源的要求,在高浓铀为燃料的微型反应堆(MNSR)的基础上,以富集度19.5％的UO2为燃料,将其堆芯低浓化并且添加水平超热中子束流治疗孔道,开展超热中子束流BNCT堆堆芯低浓化初步设计.计算BNCT堆的超热中子注量率、单位超热中子注量的快中子剂量率、单位超热中子注量的γ光子剂量率、超热中子注量与热中子的注量之比、中子束流能谱等关键参数.结果表明,该设计可以得到优良的超热中子束流.
Abstract
Based on the Miniature Neutron Source Reactor (MNSR) with high enrichment uranium (HEU) fuel and accordance with the requirements of BNCT, the 19.5% of enriched fuel UO2 fuel core for BNCT with epithermal neutron treatment beam was primary designed, the reactor core parameters such as epithermal neutron flux density,epithermal neutron flux unit of fast neutron dose rate,epithermal neutron flux unit photon dose rate of γ,epithermal neutron flux ratio of thermal neutron flux, neutron spectrum were calculated and analyzed. The results show that the design program was an excellent epithermal neutron treatment beam.
关键词
硼中子俘获治疗/微型反应堆/堆芯设计/超热中子束流Key words
BNCT/MNSR/Reactor core design/Epithermal neutron beam引用本文复制引用
基金项目
湖南省自然科学基金(07JJ6159)
湖南省重点实验室基金(2009TP4056-4)
出版年
2012
NETL
NSTL
维普
万方数据