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Shielding conceptual designs of ITER TCP ports to protect electronics

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dc.contributor.authorMartínez Albertos, Pablo
dc.contributor.authorPedroche Sánchez, Gabriel
dc.contributor.authorDremel, M.
dc.contributor.authorPearce, R.
dc.contributor.authorLoughlin, M.
dc.contributor.authorLe Tonqueze, Y.
dc.contributor.authorSanz Gozalo, Javier
dc.contributor.authorJuárez Mañas, Rafael
dc.date.accessioned2024-09-27T09:34:08Z
dc.date.available2024-09-27T09:34:08Z
dc.date.issued2022-01-18
dc.description.abstractCritical electronics of ITER Tokamak, hosted in the shielded corners (SC) of the Tokamak Building (B11), must operate under acceptable neutronic flux conditions (≤10 n⋅cm 2⋅s 1) to minimize single event effects. During machine operation and at lower level (B1), both the Torus Cryopumps (TCP) ports location within B11 and their pumping efficiency constraints are factors contributing to the radiation environment in the SC. Although previous studies have addressed the transmission of radiation out the vessel of TCP ports, none of them have assessed the impact of such radiation beyond the Port Cell. In this work, different TCP shielding configurations were evaluated at B1 level of B11 due to plasma neutrons emerging from the six TCP ports only. MCNP and dedicated computational tools were used to perform the radiation transport calculations. Albeit being a partial study, the examination of the compatibility between the TCP plasma neutron flux and the electronics limit in the SC has been addressed, while considering the combined effect of the shielding design and the building walls, lintels and doors in the results. We present a combined shielding case that reduces the neutron flux to a range of 1.3–9.3 n⋅cm 2⋅s 1 depending on the location, which is compatible with the limit while respecting pumping efficiency and assembly difficulty constraintsen
dc.description.versionversión publicada
dc.identifier.citationP. Martínez-Albertos, G. Pedroche, M. Dremel, R. Pearce, M. Loughlin, Y. Le Tonqueze, J. Sanz, R. Juárez, "Shielding conceptual designs of ITER TCP ports to protect electronics", Fusion Engineering and Design 176 (2022) 113016. https://doi.org/10.1016/j.fusengdes.2022.113016
dc.identifier.doihttps://doi.org/10.1016/j.fusengdes.2022.113016
dc.identifier.issn0920-3796
dc.identifier.urihttps://hdl.handle.net/20.500.14468/23842
dc.journal.titleFusion Engineering and Design
dc.journal.volume176
dc.language.isoen
dc.publisherElsevier
dc.relation.centerFacultades y escuelas::E.T.S. de Ingenieros Industriales
dc.relation.departmentIngeniería Energética
dc.rightsinfo:eu-repo/semantics/openAccess
dc.rights.licenseAtribución 4.0 Internacional
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/4.0/deed.es
dc.subject33 Ciencias Tecnológicas::3322 Tecnología energética
dc.subject33 Ciencias Tecnológicas
dc.subject.keywordsITERen
dc.subject.keywordsElectronicsen
dc.subject.keywordsTCPen
dc.subject.keywordsTokamaken
dc.subject.keywordsShielding analysisen
dc.titleShielding conceptual designs of ITER TCP ports to protect electronicsen
dc.typeartículoes
dc.typejournal articleen
dspace.entity.typePublication
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relation.isAuthorOfPublication4feceae8-c910-42c4-a2c5-90d13fa4c383
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relation.isAuthorOfPublication00cef46e-a8ac-4cdb-83e3-7cdda4930eb4
relation.isAuthorOfPublication.latestForDiscovery8b6fdb75-dc6b-4972-9d8b-e6029aee958a
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