Deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak

Deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak

Divertor designs involving liquid lithium have been proposed as an alternative to solid designs and wall conditioning techniques. However, Li affinity with tritium poses a risk for the fuel cycle. This study investigates deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D...

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Bibliographic Details
Main Authors: M. Morbey, F. Effenberg, S. Abe, T. Abrams, A. Bortolon, R. Hood, U. Losada, A. Nagy, J. Ren, D.L. Rudakov, M.J. Simmonds, D. Truong, T.W. Morgan
Format: Article
Language:English
Published: Elsevier 2025-06-01
Series:Nuclear Materials and Energy
Subjects:
Fuel retention
Lithium
Ion beam
Impurity powder dropper
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179125000560
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http://www.sciencedirect.com/science/article/pii/S2352179125000560

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