Analysis of burnup and economic potential of alternative fuel materials in thermal reactors

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dc.contributor.authorOggianu, SMko
dc.contributor.authorNo, Hee Cheonko
dc.contributor.authorKazimi, MSko
dc.date.accessioned2013-03-05T03:37:58Z-
dc.date.available2013-03-05T03:37:58Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2003-09-
dc.identifier.citationNUCLEAR TECHNOLOGY, v.143, no.3, pp.256 - 269-
dc.identifier.issn0029-5450-
dc.identifier.urihttp://hdl.handle.net/10203/85310-
dc.description.abstractA strategy is proposed for the assessment of nuclear fuel material economic potential use in future light water reactors (LWRs). In this methodology, both the required enrichment and the fuel performance limits are considered. In order to select the best fuel candidate, the optimal burnup that produces the lowest annual fuel cost within the burnup potential for a given fuel material and smear density ratio is determined. Several nuclear materials are presented as examples of the application of the methodology proposed in this paper. The alternative fuels considered include uranium dioxide (UO2), uranium carbide (UC) uranium nitride (UN), metallic uranium (U-Zr alloy), combined thorium and uranium oxides (ThO2/UO2), and combined thorium and uranium metals (U/Th). For these examples, a typical LWR lattice geometry in a zirconium-based cladding was assumed. The uncertainties in the results presented are large due to the scarcity of experimental data regarding the behavior of the considered materials at high burnups. Also, chemical compatibility issues are to be considered separately. The same methodology can be applied in the future to evaluate the economic potential of other nuclear fuel materials including different cladding designs, dispersions of ceramics into ceramics, dispersions of ceramics into metals, and also for geometries other than the traditional circular fuel pin.-
dc.languageEnglish-
dc.publisherAMER NUCLEAR SOCIETY-
dc.titleAnalysis of burnup and economic potential of alternative fuel materials in thermal reactors-
dc.typeArticle-
dc.identifier.wosid000184921700002-
dc.identifier.scopusid2-s2.0-0041781613-
dc.type.rimsART-
dc.citation.volume143-
dc.citation.issue3-
dc.citation.beginningpage256-
dc.citation.endingpage269-
dc.citation.publicationnameNUCLEAR TECHNOLOGY-
dc.contributor.localauthorNo, Hee Cheon-
dc.contributor.nonIdAuthorOggianu, SM-
dc.contributor.nonIdAuthorKazimi, MS-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorhigh-burnup fuels-
dc.subject.keywordAuthorfuel cycle economics-
dc.subject.keywordAuthoralternative fuel materials-
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