The effect of D2 partial pressure, deposition rate, and sample temperature on D retention in W codeposited layers

Hydrogen-isotope (HI) fuel retention in the walls of magnetic fusion devices must be minimized to achieve tritium self-sufficiency and for safety considerations. Retention in codeposited layers (i.e., layers formed from eroded material while simultaneously exposed to HIs) is projected to be a domina...

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Bibliographic Details
Main Authors: M.I. Patino, S. Dhirar, A. Založnik, B. Schwendeman, M.J. Simmonds, F. Chang, M.J. Baldwin, G.R. Tynan
Format: Article
Language:English
Published: Elsevier 2024-12-01
Series:Nuclear Materials and Energy
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Online Access:http://www.sciencedirect.com/science/article/pii/S235217912400231X
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