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Content archived on 2024-04-16

Determination of Fissile Material by Neutron Transport Interrogation

Objective

This research is concerned with non-destructive assay techniques for fissile material determination in waste material mainly in waste drums. Fissile material has been determined by active neutron interrogation with an Sb-Be neutron source which required shieldings due to the approx. 2 E12 Bq Sb-124 and had detection limits between 1 mg and 1 g fissionable material depending on sample size and matrix composition.
Neutron transport calculations at SCK/CEN Mol are intended to achieve a theoretical understanding and an improvement of the assay system with different neutron sources by modelling the neutron transport properties in the waste drum and the assay system. A replacement of the Sb-Be neutron source by other low energy neutron sources, such as Am-Li, will lead to an assay system with minimum shielding requirements and constant source strength. The replacement of the Sb-Be neutron source by Am-Li is therefore an important objective of this research. The aim of the final assay system is an easy-to-use and reliable instrument for the estimation or determination of the fissile material content of various packages, mainly waste drums.

Work programme:

Checking and optimization of the Sb-Be system by comparison with neutron transport calculations.
Active neutron interrogation with other neutron sources, in particular Am-Li and comparison with neutron transport calculations.
Modification of the system for passive neutron counting capabilities.
Test and performance of the active/passive neutron assay system with actual samples, mainly waste drums from the nuclear fuel cycle.

Call for proposal

Data not available

Coordinator

Forschungszentrum Jülich GmbH
EU contribution
No data
Address
Wilhelm-Johnen-Straße
52428 Jülich
Germany

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Total cost
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Participants (1)