Title: Scrap Neutron Multiplicity Counter: Design and Manufacture
Citation: Proceedings of the 27 ESARDA Annual Meeting, Symposium on Safeguards and Nuclear Material Management
Publisher: European Safeguards Research and Development Association (ESARDA)
Publication Year: 2005
JRC N°: JRC30787
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC30787
Type: Articles in periodicals and books
Abstract: Mixed (plutonium and uranium) oxide is processed in many of the facilities of the nuclear fuel cycle. Consequently the fissile mass of a large number of MOX and MOX scrap samples need to be accounted for and verified periodically in each facility. For MOX scrap samples the preferred method is often neutron multiplicity counting because three quantities are measured (singlet, doublet, and triplet rates). In the design of this new counter the primary objective was to achieve a maximum efficiency. However, other factors must be taken into consideration such as cost, size, weight, and in particular the requirements of the analytical model [1]. One important objective is to reduce the detector die-away time thus decreasing the number of uncorrelated (accidental) signal multiplets and consequently improving the ¿signal-to-noise¿ ratio.
JRC Directorate:Space, Security and Migration

Files in This Item:
There are no files associated with this item.

Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.