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dc.contributor.authorSedano, Luis Angel ORCID
dc.contributor.authorEsteban Alcalá, Gustavo Adolfo ORCID
dc.contributor.authorCavaro, Matthieu ORCID
dc.contributor.authorIraola de Acevedo, Eduardo ORCID
dc.contributor.authorAL AWAD, Abdulrahman ORCID
dc.contributor.authorBatet, Lluís ORCID
dc.contributor.authorGuasch, M.
dc.date.accessioned2022-08-30T11:39:56Z
dc.date.available2022-08-30T11:39:56Z
dc.date.issued2022-06
dc.identifier.citationNuclear Materials and Energy 31 : (2022) // Article ID 101185es_ES
dc.identifier.issn2352-1791
dc.identifier.urihttp://hdl.handle.net/10810/57328
dc.description.abstract[EN] The helium production rates in liquid metals (Pb-Li eutectic alloy, LLE and others) Blanket Breeders (BB) are nearly mol-to-mol linked to tritium and intimately associated with the compulsory requirement of high tritium self-sufficiency of next fusion reactors. When LLE is oversaturated and the helium solubility limit is exceeded, helium atoms can nucleate in the form of bubbles. The presence of helium bubbles within LLE channels could have severe impact on the diverse BB designs, in particular on tritium transport permeation and its recovery. Even though He is an inert gas assumed to be insoluble, the helium Henry's constant (K-H) in a liquid metal is not zero. The very low KH and difficulties to measure it has historically driven to the absence of basic data. A semi-empirical correlation is proposed providing the helium solubility (i.e.: the helium Henry's constant) based on Kumar's cohesion model using the available thermo-physical experimental solubility data for lithium, sodium, potassium, mercury. The proposed expression for eutectic lead-lithium is:& nbsp;K-H( at.fr.Pa-1) = 5.99.10-4 exp (- 1.16.delta k) exp( -54.23/RT), being K-H the Henry's constant; T [K], R [8.314 10(-3) kJ mol(-1) K-1] and delta(k) the Kumar's cohesive parameter. From a delta(k )justified value of 18.2 MPa1/2 in LLE the values for K-H range from 1.14.10(-17) to 1.35.10(-15) at.fr.Pa-1 for temperatures between 350 and 870C. The helium solubility should integrate the lead-lithium eutectic nuclear material database for fusion systems design.es_ES
dc.language.isoenges_ES
dc.publisherElsevieres_ES
dc.rightsinfo:eu-repo/semantics/openAccesses_ES
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/es/*
dc.subjectbreeding blanketes_ES
dc.subjectgaseses_ES
dc.titleThe solubility of helium in lead-lithium eutectic alloyes_ES
dc.typeinfo:eu-repo/semantics/articlees_ES
dc.rights.holder© 2022 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).es_ES
dc.rights.holderAtribución-NoComercial-SinDerivadas 3.0 España*
dc.relation.publisherversionhttps://www.sciencedirect.com/science/article/pii/S2352179122000709?via%3Dihubes_ES
dc.identifier.doi10.1016/j.nme.2022.101185
dc.departamentoesIngeniería Energéticaes_ES
dc.departamentoeuEnergia Ingenieritzaes_ES


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© 2022 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
Except where otherwise noted, this item's license is described as © 2022 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).