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dc.contributor.authorHerranz Puebla, Luis Enriquees-ES
dc.contributor.authorLinares Hurtado, José Ignacioes-ES
dc.contributor.authorMoratilla Soria, Beatriz Yolandaes-ES
dc.date.accessioned2016-01-26T11:00:55Z
dc.date.available2016-01-26T11:00:55Z
dc.date.issued01/06/2009es_ES
dc.identifier.issn1359-4311es_ES
dc.identifier.urihttp://hdl.handle.net/11531/5912
dc.descriptionArtículos en revistases_ES
dc.description.abstract.es-ES
dc.description.abstractThis century power engineering is facing up to one of the greatest challenges ever posed to humankind: the achievement of a sustainable energy system. In order to respond to this challenge, nuclear technology is designing a new generation of power plants termed Generation IV, among them high temperature gascooled reactors stand out for their potential capability to achieve an excellent thermal performance. This paper investigates the thermal and economic performance of several direct Brayton cycle configurations that could be used in future HTGRs, with special attention to the effects of inter-cooling and reheating. Among the hypotheses and assumptions taken, the adoption of the PBMR reactor parameters and settings as a reference is particularly important. All inter-cooled layouts have shown thermal efficiencies near or even higher than 50%, which means a substantial improvement with respect to non-intercooled baselines with no economic penalties. Reheating has been shown not to affect remarkably the thermal or economic plant performance under base-load operation, but it provides the plant with such a flexibility that allows its operation under the load-follow regime without heavily taxing the thermal or economic performance. Anyway, use of a multiple axes configuration instead of a single one seems to worsen plant economics and not to entail any thermal benefit.en-GB
dc.format.mimetypeapplication/pdfes_ES
dc.language.isoen-GBes_ES
dc.rightses_ES
dc.rights.uries_ES
dc.sourceRevista: Applied Thermal Engineering, Periodo: 1, Volumen: 8-9, Número: 29, Página inicial: 1759, Página final: 1765es_ES
dc.titlePower cycle assessment of nuclear high temperature gas-cooled reactorses_ES
dc.typeinfo:eu-repo/semantics/articlees_ES
dc.description.versioninfo:eu-repo/semantics/publishedVersiones_ES
dc.rights.accessRightsinfo:eu-repo/semantics/restrictedAccesses_ES
dc.keywords.es-ES
dc.keywordsPower cycles High temperature gas-cooled reactors Generation IV nuclear systemsen-GB


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