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Abstract

The research and results described in this report concern the development, evaluation and optimization of active and passive neutron detection systems for the assay of fissile material in waste packages. The starting point and impetus for this research was an existing active neutron-assay system at the KFA Jülich which uses the low-energetic photoneutrons of an Sb-Be source to induce fissions in the fissile material present in the waste package. The Sb-Be source, unfortunately, is impractical due to its high gamma dose rate therefore the replacement of the Sb-Be source by other suitable low-energetic neutron sources was an objective of this research together with the use of a similar system for passive neutron counting.

The outcome of this research is a passive neutron counter with a detection limit of 60 mg Pu (total) in 1000 s, which varies by a factor of four for different positions in a concrete-filled 200 I drum and matrix densities between 1 g/cm{3} and 4 g/cm{3}. In the active assay system, the accelerator reaction Li(p,n)Be was confirmed as an alternative neutron source. .

Additional information

Authors: ODOJ R ET AL, Forschungszentrum Jülich (DE);MANDOKI R ET AL, SCK/CEN, Mol (BE)
Bibliographic Reference: EUR 17560 EN (1997) 38pp., FS, ECU 8.50
Availability: Available from the (2)
ISBN: ISBN 92-827-9979-4
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