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HELIUM THERMAL DESORPTION FROM TUNGSTEN AFTER ION BEAM IRRADIATION AT ELEVATED TEMPERATURES

dc.contributor.authorRyabtsev, S. A.
dc.contributor.authorGasparyan, Yu. M.
dc.contributor.authorHarutyunyan, Z. R.
dc.contributor.authorEfimov, V. S.
dc.contributor.authorAksenova, A. S.
dc.contributor.authorPisarev, A. A.
dc.contributor.authorПисарев, Александр Александрович
dc.contributor.authorЕфимов, Виталий Сергеевич
dc.contributor.authorГаспарян, Юрий Микаэлович
dc.contributor.authorАрутюнян, Зорий Робертович
dc.date.accessioned2024-11-13T11:00:44Z
dc.date.available2024-11-13T11:00:44Z
dc.date.issued2019
dc.description.abstractHelium (He) is a product of deuterium-tritium reaction, so appearance of helium impurities will be unavoidable. In addition to He implantation from fusion plasma, He can be introduced into material by both neutron irradiation and tritium radioactive decay. Presence of He in plasma-facing materials may significantly influence their mechanical properties and surface morphology [1, 2], as well as hydrogen isotope recycling [3, 4]. Tungsten (W) will be used as a plasma-facing material in ITER divertor [5], and it is considered also for application in future fusion devices. Therefore, investigation of He interaction with W is of great interest.
dc.identifier.citationHelium thermal desorption from tungsten after ion beam irradiation at elevated temperatures [Text]. / Ryabtsev S.A. [et al.] // Взаимодействие ионов с поверхностью ВИП-2019: труды XXIV Международной конференции Том 1. - 2019. - С. 66-69
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/16150
dc.publisherНИЯУ МИФИ
dc.subjectКонференции НИЯУ МИФИ
dc.titleHELIUM THERMAL DESORPTION FROM TUNGSTEN AFTER ION BEAM IRRADIATION AT ELEVATED TEMPERATURES
dc.typeArticle
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