Extension of the SCK•CEN spent fuel inventory library

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Abstract

SCK•CEN is performing R&D work related to the development of Non Destructive Assay on spent fuel elements. Due to difficulty in accessing spent fuel, having an accurate and validated model of the measurement equipment and a characterization of the source term is important for this type of studies. To better understand and develop methods based on neutron counting and gamma spectroscopy, a significant effort was done to determine the source terms associated to spent fuel with depletion and evolution code calculations. This paper reports about the extension of the SCK•CEN spent fuel inventory library with the ORIGEN-ARP code. The cases considered a Low Enriched Uranium 17×17 PWR fuel with an initial enrichment of 2.0, 2.5 and 3.0 %. This set of enrichments complements the data published previously for enrichments between 3.5 % and 5 %. In addition, results obtained with Mixed Oxide (MOX) fuel are presented and discussed. The impact of the initial enrichment, for LEU fuel, and the Pu mass, for MOX fuel, on the neutron emission and production of the main neutron emitters, are also studied.

Details

Original languageEnglish
Title of host publicationESARDA 37th Annual Meeting Proceedings
Place of PublicationLuxembourg
Pages225-234
Publication statusPublished - 6 Aug 2015
Event2015 - ESARDA - European Safeguards Research & Development Association: 37th ESARDA Annual Meeting - Midland Hotel, Manchester, United Kingdom
Duration: 19 May 201521 May 2015
https://esarda.jrc.ec.europa.eu/index.php?option=com_content&view=article&id=266&Itemid=336

Conference

Conference2015 - ESARDA - European Safeguards Research & Development Association
CountryUnited Kingdom
CityManchester
Period2015-05-192015-05-21
Internet address

Keywords

  • Evolution and depletion calculation, Spent Fuel Inventory, Neutron emission, Gamma emission, Spent Fuel, Non Destructive Assay

ID: 256922