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Deterministic neutron transport and burnup code coupling assessment

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Deterministic neutron transport and burnup code coupling assessment

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dc.contributor.author Vivancos-Grau, Arturo es_ES
dc.contributor.author Miró Herrero, Rafael es_ES
dc.contributor.author Barrachina, Teresa es_ES
dc.contributor.author Bernal, Álvaro es_ES
dc.contributor.author Verdú Martín, Gumersindo Jesús es_ES
dc.date.accessioned 2024-06-08T18:07:36Z
dc.date.available 2024-06-08T18:07:36Z
dc.date.issued 2024-04 es_ES
dc.identifier.issn 0306-4549 es_ES
dc.identifier.uri http://hdl.handle.net/10251/204831
dc.description.abstract [EN] Nuclide evolution is a key aspect in nuclear reactor design and operation. Burnup (or depletion) codes evaluate the isotopic inventory evolution. The inherent need for nuclear safety, the development in computational capabilities, and new discoveries in related areas, such as mathematical methods, result in constant software re-evaluation and improvement. Now, many stochastic-based burnup codes are being developed in comparison to deterministic-based ones, which also present advantages and interesting aspects. In this work, nuclear li-braries, processing requirements, data workflow, and methodologies are studied for the development of a brand-new burnup code linked to the VALKIN-FVM-Sn deterministic transport code. As a result, the requirements to create, and couple, a burnup code have been assessed, establishing a methodology. The burnup code has been developed and contrasted with an industry reference. The resulting coupling is a lattice code foundation to be used in a Multiphysics platform. es_ES
dc.description.sponsorship This work has been partially supported by Grant PGC2018-096437-B-I00-AR funded by MCIN/AEI/10.13039/501100011033 and by "ERDF A way of making Europe", by the "European Union" and Grant PRE2019-089431 funded by MCIN/AEI/10.13039/501100011033 and by "ESF Investing in your future". es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Annals of Nuclear Energy es_ES
dc.rights Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) es_ES
dc.subject Depletion es_ES
dc.subject Burnup es_ES
dc.subject Neutron transport es_ES
dc.subject Transition matrix es_ES
dc.subject FVM es_ES
dc.subject DO es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Deterministic neutron transport and burnup code coupling assessment es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.anucene.2023.110291 es_ES
dc.relation.projectID info:eu-repo/grantAgreement/AEI/Plan Estatal de Investigación Científica y Técnica y de Innovación 2017-2020/PGC2018-096437-B-I00/ES/APLICACION INTEGRADA DE FISICA DE REACTORES PARA SIMULACIONES A GRAN ESCALA/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/AEI//PRE2019-089431/ es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Escuela Técnica Superior de Ingenieros Industriales - Escola Tècnica Superior d'Enginyers Industrials es_ES
dc.description.bibliographicCitation Vivancos-Grau, A.; Miró Herrero, R.; Barrachina, T.; Bernal, Á.; Verdú Martín, GJ. (2024). Deterministic neutron transport and burnup code coupling assessment. Annals of Nuclear Energy. 198. https://doi.org/10.1016/j.anucene.2023.110291 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1016/j.anucene.2023.110291 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 198 es_ES
dc.relation.pasarela S\507270 es_ES
dc.contributor.funder European Social Fund es_ES
dc.contributor.funder Agencia Estatal de Investigación es_ES
dc.contributor.funder European Regional Development Fund es_ES
dc.contributor.funder Universitat Politècnica de València es_ES


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