Publication:
PLASMA-WALL INTERACTION STUDIES AT JET-ILW IN A VIEW OF UPCOMING D, H AND T EXPERIMENTAL CAMPAIGNS

dc.contributor.authorBORODKINA, I.
dc.contributor.authorDOUAI, D.
dc.contributor.authorBORODIN, D.
dc.date.accessioned2025-03-17T09:07:04Z
dc.date.available2025-03-17T09:07:04Z
dc.date.issued2018
dc.description.abstractThe Joint European Torus (JET) is the largest tokamak in use and currently the only one capable of handling tritium (T). JET equipped with the ITER-like wall (ILW) utilizing the same as ITER material combination: tungsten (W) divertor and beryllium (Be) main chamber, provides the most relevant environment for ITER plasma-wall interaction studies. In 2017 the coordinated on-site and off-site analysis and modelling activities in the frame of the fifteen researcher groups named as “analysis&modelling tasks” were performed: analysis of past experiments & assess of JET D-T campaign readiness, predictive modelling with physics based integrated (edge-core, wall-SOL) codes for JET and ITER, preparation of experimental proposals for C38- C42 D-H-T-H-D upcoming campaigns.
dc.identifier.citationBorodkina I. PLASMA-WALL INTERACTION STUDIES AT JET-ILW IN A VIEW OF UPCOMING D, H AND T EXPERIMENTAL CAMPAIGNS [Teкст]. / Borodkina I., Douai D., Borodin D. // Взаимодействие плазмы с поверхностью: сборник научных трудов XXI конференции. - 2018. - С. 77-80
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/36674
dc.publisherНИЯУ МИФИ
dc.subjectКонференции НИЯУ МИФИ
dc.titlePLASMA-WALL INTERACTION STUDIES AT JET-ILW IN A VIEW OF UPCOMING D, H AND T EXPERIMENTAL CAMPAIGNS
dc.typeArticle
dspace.entity.typePublication
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