Mostra i principali dati dell'item

dc.contributor.authorZurrón Cifuentes, Óscar es_ES
dc.contributor.authorSánchez León, José Guillermo es_ES
dc.contributor.authorÁlvaro, Carolinaes_ES
dc.date.accessioned2009-03-03es_ES
dc.date.accessioned2009-10-14T11:53:41Z
dc.date.available2009-10-14T11:53:41Z
dc.date.issued2003es_ES
dc.identifier.citationZurrón, O., Sánchez León, J.G. y Álvaro, C. (2003). Use of International Criticality Safety Benchmark Evaluation Project benchmarks for the validation of CSAS26 (Scale 4.4a) for configurations of low-enriched uranium. "Nuclear science and engineering" 145, 153-159.es_ES
dc.identifier.urihttp://hdl.handle.net/10366/55631es_ES
dc.description[ES]El artículo presenta la validación del módulo de control CSAS26 de SCALE 4.4a para el cálculo en ordenador personal, como un ejemplo de la aplicación del proyecto ICSBEP. Como resultado el módulo es considerado como un método calculacional bastante adecuado para la aplicación del análisis criticidad- seguridad al uranio de enriquecimiento bajo.es_ES
dc.description.abstract[EN]As an example of the application of the lntemational Criticality Safety Benchmark Evaluation Project (ICSBEP) work to the nuclear industry, the validation of the control module CSAS26 of SCALE 4.4a for criticality calculations on a personal computer platform is presented. This work has been done using the models of critical experiments being compiled by the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) since 1992. The description and results of this compilation were first presented during the Fifth lntemational Conference on Nuclear Criticality Safety(ICNC'95). Out of 2881 critical configurations included in the latest edition (September 2002) of the ICSBEP "lntemational Handbook of Evaluated Criticality Safety Benchmark Experiments." NEA/NSC/ DOC(95)03, OECD/NEA, 131 have been selectedfor the CSAS26 validation. The selected critical experiments have characteristics similar to the systems to be simulated with CSAS26 for low-enriched uranium (LEU) fuel fabrication applications. They represent both homogeneous configurations and hexagonallypitched rod lattices of low-enriched (from 1.60 to 5.00 wt% 235U) U02 with several absorbers. The statistical uncertainties related to the application of CSAS26 for criticality calculations are also evaluated. The great number of cases involved allows an exhaustive statistical treatment of the data, including the analysis of correlations related to the type of system being simulated. The statistical uncertainties found are very small. As a result, the module CSAS26 is considered as a quite suitable calculationalmethod for application to criticality safety analysis at LEU facilities.es_ES
dc.format.extent7 p.es_ES
dc.format.mimetypeapplication/pdfes_ES
dc.languageIngléses_ES
dc.language.isoenges_ES
dc.publisherAmerican Nuclear Society (La Grange Park, Estados Unidos)es_ES
dc.rightsAttribution-NonCommercial-NoDerivs 3.0 Unported
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/3.0/
dc.subjectlntemational Criticality Safety Benchmark Evaluation Projectes_ES
dc.subjectCSAS26es_ES
dc.subjectLow-enriched uraniumes_ES
dc.subjectUranio enriquecidoes_ES
dc.titleUse of International Criticality Safety Benchmark Evaluation Project benchmarks for the validation of CSAS26 (Scale 4.4a) for configurations of low-enriched uraniumes_ES
dc.typeinfo:eu-repo/semantics/articlees_ES
dc.rights.accessRightsinfo:eu-repo/semantics/openAccesses_ES


Files in questo item

Thumbnail

Questo item appare nelle seguenti collezioni

Mostra i principali dati dell'item

Attribution-NonCommercial-NoDerivs 3.0 Unported
Excepto si se señala otra cosa, la licencia del ítem se describe como Attribution-NonCommercial-NoDerivs 3.0 Unported