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dc.contributor.author | García Fajardo, Laura![]() |
es_ES |
dc.contributor.author | Pérez-Curbelo, Jesús![]() |
es_ES |
dc.contributor.author | Garcia Hernandez, Carlos Rafael![]() |
es_ES |
dc.contributor.author | Escrivá Castells, Facundo Alberto![]() |
es_ES |
dc.contributor.author | Rosales, J.![]() |
es_ES |
dc.contributor.author | Abánades, Alberto![]() |
es_ES |
dc.date.accessioned | 2017-09-29T07:44:55Z | |
dc.date.available | 2017-09-29T07:44:55Z | |
dc.date.issued | 2012-12 | |
dc.identifier.issn | 0029-5493 | |
dc.identifier.uri | http://hdl.handle.net/10251/88236 | |
dc.description.abstract | [EN] One of the main problems that should be addressed in the use of nuclear fuels for heat and electricity production is the management of nuclear waste from conventional nuclear power plants and its inventory minimization. Fast reactors and Accelerator Driven Systems (ADSs) are the main options for reducing the long-lived radioactive waste inventory. In previous studies, the conceptual design of a Transmutation Advanced Device for Sustainable Energy Applications (TADSEA) has been made. The TADSEA is a pebble-bed ADS cooled by helium and moderated by graphite; it uses as fuel small amounts of transuranic elements in the form of TRISO particles, confined in 3 cm radius graphite pebbles. It has been conceived for Plutonium (Pu) and Minor Actinides (MA) transmutation and for achieving very high helium temperatures at the core's outlet to match the thermal requirements for hydrogen production by high temperature electrolysis (HTE) or by the iodine-sulfur (I-S) thermo-chemical cycle. In this paper, a geometrical method for calculating the real number of pebbles that fit in a cylindrical ADS core, according to its size and pebble configuration, is described. Based on its results, the packing fraction influence on the TADSEA's main work parameters is studied, and the redesign of the previous configuration is done in order to maintain the exit thermal power established in the preliminary design. Results have shown the capability of the system to reach coolant outlet temperatures high enough for its application to hydrogen production. | es_ES |
dc.description.sponsorship | This work has been carried out in the framework of technological international cooperation supported by the MAEC-AECID grant program of the Spanish Ministry of Foreign Affairs and International Cooperation, with the support of the International Cooperation Program of the UPV. Authors also like to thank the National Institute of Science and Technology of Innovative Nuclear Reactors (Instituio Nacional de Ciencia e Tecnologia de Reatores Nucleares Inovadores), Brazil, for the financial support to one author's attendance at Encontro Plenario do INCT de Reatores Nucleares Inovadores 2012, Brazil. | en_EN |
dc.language | Inglés | es_ES |
dc.publisher | Elsevier | es_ES |
dc.relation.ispartof | Nuclear Engineering and Design | es_ES |
dc.rights | Reserva de todos los derechos | es_ES |
dc.subject | HYDROGEN | es_ES |
dc.subject | FUEL | es_ES |
dc.subject | CHALLENGES | es_ES |
dc.subject | CYCLE | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.title | Calculation of the packing fraction in a pebble-bed ADS and redesigning of the Transmutation Advanced Device for Sustainable Energy Applications (TADSEA) | es_ES |
dc.type | Artículo | es_ES |
dc.identifier.doi | 10.1016/j.nucengdes.2012.07.002 | |
dc.rights.accessRights | Cerrado | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Escuela Técnica Superior de Ingenieros Industriales - Escola Tècnica Superior d'Enginyers Industrials | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Instituto de Ingeniería Energética - Institut d'Enginyeria Energètica | es_ES |
dc.description.bibliographicCitation | Garcia Fajardo, L.; Pérez-Curbelo, J.; Garcia Hernandez, CR.; Escrivá Castells, FA.; Rosales, J.; Abánades, A. (2012). Calculation of the packing fraction in a pebble-bed ADS and redesigning of the Transmutation Advanced Device for Sustainable Energy Applications (TADSEA). Nuclear Engineering and Design. 253:142-152. doi:10.1016/j.nucengdes.2012.07.002 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.publisherversion | http://dx.doi. org/10.1016/j.nucengdes.2012.07.002 | es_ES |
dc.description.upvformatpinicio | 142 | es_ES |
dc.description.upvformatpfin | 152 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 253 | es_ES |
dc.relation.senia | 237656 | es_ES |
dc.contributor.funder | Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores, Brasil | es_ES |
dc.contributor.funder | Ministerio de Asuntos Exteriores y Cooperación | es_ES |
dc.contributor.funder | Universitat Politècnica de València | es_ES |