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New method for estimating uranium and plutonium masses using differential die-away signals

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dc.contributor.authorSeol, Sehwan-
dc.contributor.authorKim, Jae Chang-
dc.contributor.authorBernaski, Junehyung Lee-
dc.contributor.authorKim, Yong Kyun-
dc.contributor.authorHong, Ser Gi-
dc.date.accessioned2026-06-22T01:00:21Z-
dc.date.available2026-06-22T01:00:21Z-
dc.date.issued2026-05-
dc.identifier.issn1738-5733-
dc.identifier.issn2234-358X-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/213856-
dc.description.abstractThis study presents a novel method for estimating the masses of uranium-235 and total plutonium in spent nuclear fuel assemblies using only Differential Die-Away (DDA) analysis results and cooling time without relying on passive or delayed neutron measurements. A database of DDA signals was generated through MCNP6 simulations based on spent nuclear fuel compositions derived from ORIGAMI depletion calculations under a wide range of initial enrichments, burnups, and cooling times. The correlations were developed between DDA results (i.e., die-away time and total neutron counts) and the isotopic masses. For235U, a linear function of the signal ratio was used with the coefficients depending on cooling time. For Pu, a separate correlation was introduced using the die-away time difference between spent and fresh fuels, which required an estimation of initial enrichment. A Gaussian Process Regression (GPR) model was trained for this purpose, achieving high accuracy. Validation with 50 independent SNFs showed high prediction performance with maximum relative errors of 7.52 % and 2.41 % for235U and Pu, respectively. This method provides a non-destructive and efficient technique for characterizing spent nuclear fuel assemblies, offering potential applications in nuclear safeguards, spent fuel management, and nuclear material accountancy.-
dc.format.extent10-
dc.language영어-
dc.language.isoENG-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleNew method for estimating uranium and plutonium masses using differential die-away signals-
dc.typeArticle-
dc.publisher.location대한민국-
dc.identifier.doi10.1016/j.net.2025.104110-
dc.identifier.scopusid2-s2.0-105028329845-
dc.identifier.wosid001663848300001-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.58, no.5, pp 1 - 10-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume58-
dc.citation.number5-
dc.citation.startPage1-
dc.citation.endPage10-
dc.type.docTypeArticle-
dc.identifier.kciidART003325092-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordAuthorDifferential die-away analysis-
dc.subject.keywordAuthorNon-destructive assay-
dc.subject.keywordAuthorSpent nuclear fuel-
dc.subject.keywordAuthorCorrelation analysis-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S1738573325006783?via%3Dihub-
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