摘要
利用二维中子-光子输运程序DOT3.5计算和分析HT-7U在D—D放电运行时实验大厅内外的中子、光子通量及剂量当量率的空间分布,并评估大厅顶部不同防护材料的屏蔽效果,为辐射防护设计提供参考。
The distributions of neutron flux, r flux and dose rate at the neighbourhoed of HT-7U device are calculated and analyzed by using the two-dimensional neutron/photon transport code DOT3.5. Different shielding materials and their thicknesses are compared and optimized to give a reference to the shielding design of HT- 7U device.
出处
《核技术》
CSCD
北大核心
2000年第8期531-535,共5页
Nuclear Techniques