Abstract
Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
