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Microstructure evolution and deuterium trapping in low-energy cascades after irradiation of SS316 stainless steel

Microstructure evolution and deuterium trapping in low-energy cascades after irradiation of SS316 stainless steel

The release profile of deuterium from SS316 austenitic steel irradiated with low-energy deuterium ions was studied using thermal desorption spectroscopy as well as steel microstructure evolution after deuterium implantation and subsequent annealing by means of transmission electron microscopy. It wa...

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Bibliographic Details
Main Authors: Karpov, S.A., Tolstolutskaya, G.D., Sungurov, B.S., Ruzhytskiy, V.V.
Format: Article
Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2017
Series:Вопросы атомной науки и техники
Subjects:
Физика радиационных повреждений и явлений в твердых телах
Online Access:http://dspace.nbuv.gov.ua/handle/123456789/134047
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Summary:The release profile of deuterium from SS316 austenitic steel irradiated with low-energy deuterium ions was studied using thermal desorption spectroscopy as well as steel microstructure evolution after deuterium implantation and subsequent annealing by means of transmission electron microscopy. It was found that dislocation loops are predominant observed defects in SS316 steel irradiated to dose of ~ 1 dpa. The temperature range of deuterium retention is 300 600 K. Thermal desorption measurements show slightly-resolved stage of deuterium release with a maximum at temperature near 400 K. The energies of deuterium de-trapping have been analyzed using numerical simulations based on diffusion-trapping model.

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