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...
Збережено в:
| Дата: | 2017 |
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| Автори: | , , , |
| Формат: | Стаття |
| Мова: | English |
| Опубліковано: |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2017
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| Назва видання: | Вопросы атомной науки и техники |
| Теми: | |
| Онлайн доступ: | http://dspace.nbuv.gov.ua/handle/123456789/134047 |
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| Назва журналу: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Цитувати: | Microstructure evolution and deuterium trapping in low-energy cascades after irradiation of SS316 stainless steel / S.A. Karpov, G.D. Tolstolutskaya, B.S. Sungurov, V.V. Ruzhytskiy // Вопросы атомной науки и техники. — 2017. — № 2. — С. 36-40. — Бібліогр.: 19 назв. — англ. |
Репозитарії
Digital Library of Periodicals of National Academy of Sciences of Ukraine| Резюме: | 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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