Publication: Deuterium trapping in co-deposited layers of ITER-relevant materials
Дата
2021
Авторы
Krat, S. A.
Prishvitsyn, A. S.
Vasina, Ya. A.
Fefelova, E. A.
Gasparyan, Yu. M.
Pisarev, A. A.
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Издатель
НИЯУ МИФИ
Аннотация
Hydrogen isotope accumulation in fusion devices is a serious problem. Because deuterium-tritium mixture will be a working gas in future fusion devices, including ITER tokamak, tritium accumulation is an issue from the perspective of radiation safety. In total, only 700 grams of tritium are allowed to be present in ITER vessel at any time, with additional 120 in the cryopumps, and 180 grams allocated to measurement error, to the total of 1000 grams.
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Конференции НИЯУ МИФИ
Цитирование
Deuterium trapping in co-deposited layers of ITER-relevant materials [Text]. / Krat S.A. [et al.] // Взаимодействие ионов с поверхностью ВИП: труды XXV Международной конференции Том 3 -2021. - 2021. - С. 13-18