期刊论文

Yu, T.

中文

核动力工程

0258-0926

2012

33

3

17-20+37

10.3969/j.issn.0258-0926.2012.03.004

07JJ6159:湖南省自然科学基金 2009TP4056-4:湖南省重点实验室基金

本校为第一且通讯机构

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.

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 UO 2 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 ...