Study of the neutron flux in a model for a 252Cf cold neutron source

被引:1
|
作者
Robinson, L [1 ]
Johnson, E
Zhao, L
机构
[1] Florida A&M Univ, Inst Environm Sci, Tallahassee, FL 32307 USA
[2] Oak Ridge Natl Lab, Div Chem & Analyt Sci, Oak Ridge, TN 37831 USA
关键词
Inorganic Chemistry; Polyethylene; Activation Analysis; Neutron Activation; Analysis Measurement;
D O I
10.1007/BF02385351
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The flux of cold neutrons that is obtainable from various high energy neutron sources is studied for a particular model of a cold neutron source when the cold moderation region of the apparatus is at 20, 70, and 298K. The maximum flux obtained with a californium-252 source was 2.7.10(-3) cold neutron per (cm(2).second (source neutron)). This flux was obtained when the cold moderation region of the apparatus was at 20K and when the thermal moderator is either polyethylene or trimethylbenzene and the cold moderator is polyethylene. This flux should allow sensitive prompt and delayed neutron activation analysis measurements.
引用
收藏
页码:25 / 28
页数:4
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