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dc.contributor.authorCastillo, Alejandro
dc.contributor.authorOrtiz-Servin, Juan José
dc.contributor.authorNovoa, Pavel
dc.contributor.authorPelta Mochcovsky, David Alejandro 
dc.date.accessioned2024-01-25T10:36:03Z
dc.date.available2024-01-25T10:36:03Z
dc.date.issued2023-08-26
dc.identifier.urihttps://hdl.handle.net/10481/87263
dc.description.abstractA configuration for the integral problem of in-core fuel management consists of a fuel lattice and a fuel assembly designs, as well as a fuel reload and a control rod pattern design, so that the different criteria for the proper operation of a BWR reactor are met. Such a configuration or solution is not unique. There is an universe of potential candidate solutions that solve the problem in different ways. Departing from a database of candidate configurations, we describe and show the application of a multicriteria analysis methodology based on intervals and possibility function. The nuclear engineer must define his/her preferences in terms of the relevance assigned to the configurations’ features and next, using the methodology, those configurations are ranked. Besides this, the methodology can help us to identify the role that play some fuel lattice variables into the in-core fuel problem performance.es_ES
dc.description.sponsorshipD. Pelta and P. Novoa acknowledge support from projects PID2020-112 754 GB-I0, MCIN/AEI /10.13039/501100011033 and FEDER/Junta de Andalucía - Consejería de Transformaci´on Econ´omica, Industria, Conocimiento y Universidades / Proyecto (B-TIC-640-UGR20)es_ES
dc.language.isoenges_ES
dc.publisherElsevier B.Ves_ES
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs 3.0 Licensees_ES
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/es_ES
dc.titleA methodology for the analysis of In-Core fuel management configurations in BWR’ses_ES
dc.typejournal articlees_ES
dc.rights.accessRightsopen accesses_ES
dc.identifier.doihttps://doi.org/10.1016/j.nucengdes.2023.112529
dc.type.hasVersionSMURes_ES


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