Вплив водню, орієнтації гідридів та температури на опір малоциклової втоми оболонок твелів зі сплаву Zr-1%Nb

Low-cycle fatigue testing was conducted on annular samples with an outer diameter of 9.13 mm, a wall thickness of 0.68 mm and a width of 2.7 mm, namely: non-hydrogenated samples (cut out of standard Zr‑1%Nb cladding tubes); hydrogenated samples with a hydrogen concentration of 50 ... 400 ppm; sample...

Повний опис

Збережено в:
Бібліографічні деталі
Дата:2021
Автори: Riedkina, G., Grytsyna, V., Klymenko, S., Chernyayeva, Т.
Формат: Стаття
Мова:English
Опубліковано: State Scientific and Technical Center for Nuclear and Radiation Safety 2021
Онлайн доступ:https://nuclear-journal.com/index.php/journal/article/view/751
Теги: Додати тег
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Назва журналу:Nuclear and Radiation Safety

Репозитарії

Nuclear and Radiation Safety
Опис
Резюме:Low-cycle fatigue testing was conducted on annular samples with an outer diameter of 9.13 mm, a wall thickness of 0.68 mm and a width of 2.7 mm, namely: non-hydrogenated samples (cut out of standard Zr‑1%Nb cladding tubes); hydrogenated samples with a hydrogen concentration of 50 ... 400 ppm; samples cut out from hydrogenated dummy claddings after hydride reorientation tests performed according to various test modes. The tests were conducted at the temperatures of 25, 180, 350, 400 and 450 °С. The results obtained demonstrate that with increasing the hydrogen content in Zr-1%Nb alloy claddings the fatigue life increases.