Full metadata record
DC FieldValueLanguage
dc.contributor.authorSCHILLEBEECKX PETERen_GB
dc.contributor.authorVERWERFT M.en_GB
dc.contributor.authorZEROVNIK GASPERen_GB
dc.contributor.authorPARTHOENS Y.en_GB
dc.contributor.authorPEDERSEN BENTen_GB
dc.contributor.authorALAERTS GERYen_GB
dc.contributor.authorCOOLS GERRYen_GB
dc.contributor.authorGOVERS KEVINen_GB
dc.contributor.authorPAEPEN JANen_GB
dc.contributor.authorVARASANO GIOVANNIen_GB
dc.contributor.authorWYNANTS RUUDen_GB
dc.date.accessioned2020-10-01T00:02:55Z-
dc.date.available2020-09-30en_GB
dc.date.available2020-10-01T00:02:55Z-
dc.date.created2020-09-29en_GB
dc.date.issued2020en_GB
dc.date.submitted2020-09-05en_GB
dc.identifier.isbn978-92-76-22349-8 (online)en_GB
dc.identifier.issn1831-9424 (online)en_GB
dc.identifier.otherEUR 30379 ENen_GB
dc.identifier.otherOP KJ-NA-30379-EN-N (online)en_GB
dc.identifier.urihttps://publications.jrc.ec.europa.eu/repository/handle/JRC121586-
dc.description.abstractA method to determine the neutron production rate of a sample of spent nuclear fuel by means of non-destructive analysis conducted under controlled-area conditions is described, validated and demonstrated. A standard neutron well-counter designed for routine nuclear safeguards applications is applied. The method relies on a transfer procedure that is adapted to the hot-cell facilities at the laboratory for high and medium level activity of the SCK CEN. The sample transfer and measurement procedures are described together with results of Monte Carlo simulations. Experiments with radionuclide sources were carried out at the Joint Research Centre to test the procedures and to determine the performance characteristics of the detection device. Finally, measurements of a segment of a spent nuclear fuel rod were carried out at the SCK CEN to validate and demonstrate the method.en_GB
dc.description.sponsorshipJRC.G.2-Standards for Nuclear Safety, Security and Safeguardsen_GB
dc.format.mediumOnlineen_GB
dc.languageENGen_GB
dc.publisherPublications Office of the European Unionen_GB
dc.relation.ispartofseriesJRC121586en_GB
dc.titleA non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditionsen_GB
dc.typeEUR - Scientific and Technical Research Reportsen_GB
dc.identifier.doi10.2760/614853 (online)en_GB
JRC Directorate:Nuclear Safety and Security

Files in This Item:
File Description SizeFormat 
npr_snf_report_final.pdf2.43 MBAdobe PDFView/Open


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