Monitoring fissile and matrix materials in closed containers by means of pulsed neutron sources
Journal article, 2013

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.©2013 Springer Science+Business Media New York.

Author

V.F. Batyaev

O.V. Bochkarev

S.V. Sklyarov

V.L. Romodanov

Dina Chernikova

Chalmers, Applied Physics, Nuclear Engineering

Atomic Energy

1063-4258 (ISSN) 1573-8205 (eISSN)

Vol. 115 2 116-122

Subject Categories

Other Engineering and Technologies

DOI

10.1007/s10512-013-9758-z

More information

Created

10/7/2017