{"title":"Determination of burn-up of irradiated fuel elements by pulsed neutron interrogation","authors":"W. Rotter","doi":"10.1016/0302-2927(74)90068-3","DOIUrl":null,"url":null,"abstract":"<div><p>An experimental study is described which could provide a method for the non-destructive assay of the fissile content in depleted fuel elements of power reactors.</p><p>The basis of the method is a comparison of pulsed prompt neutron responses of the unknown fuel element with responses of known standards.</p><p>The method has been tested on non-irradiated BR2 fuel elements simulating two types of examination: </p><ul><li><span>1.</span><span><p>(a) determination of the remaining <sup>235</sup>U-content and of the associated boron content (residual burnable poison);</p></span></li><li><span>2.</span><span><p>(b) classification of poisoned CERMET-elements with respect to increasing burn-up, without discrimination of uranium and poison effects.</p></span></li></ul><p>An installation is described which should allow determination of burn-up values up to 50 per cent within reasonable measuring times and with acceptable accuracy.</p></div>","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 7","pages":"Pages 451-458"},"PeriodicalIF":0.0000,"publicationDate":"1974-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90068-3","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Science and Engineering","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0302292774900683","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1
Abstract
An experimental study is described which could provide a method for the non-destructive assay of the fissile content in depleted fuel elements of power reactors.
The basis of the method is a comparison of pulsed prompt neutron responses of the unknown fuel element with responses of known standards.
The method has been tested on non-irradiated BR2 fuel elements simulating two types of examination:
1.
(a) determination of the remaining 235U-content and of the associated boron content (residual burnable poison);
2.
(b) classification of poisoned CERMET-elements with respect to increasing burn-up, without discrimination of uranium and poison effects.
An installation is described which should allow determination of burn-up values up to 50 per cent within reasonable measuring times and with acceptable accuracy.
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