Monitoring Fissile and Matrix Materials in Closed Containers by Means of Pulsed Neutron Sources

被引:0
|
作者
V. F. Batyaev
O. V. Bochkarev
S. V. Sklyarov
V. L. Romodanov
D. N. Chernikova
机构
[1] Dukhov All-Russia Research Institute of Automatics (VNIIA),
[2] National Nuclear Research University – Moscow Engineering-Physics Institute (NIYaU MIFI),undefined
来源
Atomic Energy | 2013年 / 115卷
关键词
Uranium; Matrix Material; Empty Container; Pulse Neutron; Fission Neutron;
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中图分类号
学科分类号
摘要
Computational and experimental studies of the possibility of determining the fissile and matrix materials by means of differential neutron attenuation are presented. The time response of 235U fission under the action of 14 MeV neutrons from an ING-07T pulsed neutron generator, fabricated by VNIIA, on a 70-liter steel container holding uranium in graphite, iron and polyethylene matrices is analyzed. It is shown that milligram quantities of 235U can be detected and the matrix type and density as well as the location of fissile material inside a container can be determined.
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页码:116 / 122
页数:6
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