{"title":"Measurement of low enriched uranium fuel pellets","authors":"I. Badawy, W. El-Gammal","doi":"10.1109/NRSC.1999.760955","DOIUrl":null,"url":null,"abstract":"Fresh low enriched uranium fuel pellets for a nuclear reactor have been measured by a passive non destructive assay technique. It is based on the measurement of a certain characteristic gamma-rays peak of the U-235 in the pellets at energy of about 185.7 keV. The technique does not require nuclear material standards for the measurement of U-235 enrichment. The measurement employs a high resolution Ge detector gamma-ray spectrometer. The obtained values of U-235 enrichment are comparable in accuracy with results by the relative methods which require nuclear material standards. The present work may be applied as a method of control of nuclear material at the production level. Also, it can be used for nuclear material safeguards and inventory verification purposes.","PeriodicalId":250544,"journal":{"name":"Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249)","volume":"70 5 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1999-02-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"4","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/NRSC.1999.760955","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 4
Abstract
Fresh low enriched uranium fuel pellets for a nuclear reactor have been measured by a passive non destructive assay technique. It is based on the measurement of a certain characteristic gamma-rays peak of the U-235 in the pellets at energy of about 185.7 keV. The technique does not require nuclear material standards for the measurement of U-235 enrichment. The measurement employs a high resolution Ge detector gamma-ray spectrometer. The obtained values of U-235 enrichment are comparable in accuracy with results by the relative methods which require nuclear material standards. The present work may be applied as a method of control of nuclear material at the production level. Also, it can be used for nuclear material safeguards and inventory verification purposes.