Отправить статью по E-mail The Accumulation and Annealing of Radiation-Induced Defects and the Effect of Hydrogen on the Physicomechanical Properties of the V−4Ti−4Cr and V−10Ti−5Cr Vanadium-Based Alloys under Low-Temperature (at 77 K) Neutron Irradiation
- Авторы: Arbuzov V.L.1, Goshchitskii B.N.1, Sagaradze V.V.1, Danilov S.E.1, Zuev Y.N.2, Kar’kin A.E.1, Parkhomenko V.D.1, Kozlov A.V.3, Chernov V.M.4
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Учреждения:
- Institute of Metal Physics, Ural Branch
- Russian Federal Nuclear Center—Zababakhin All-Russian Scientific Research Institute of Technical Physics
- OAO Institute for Reactor Materials
- Bochvar All-Russian Research Institute for Inorganic Materials
- Выпуск: Том 117, № 3 (2016)
- Страницы: 299-306
- Раздел: Strength and Plasticity
- URL: https://journals.rcsi.science/0031-918X/article/view/166680
- DOI: https://doi.org/10.1134/S0031918X16030030
- ID: 166680
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Аннотация
The processes of the accumulation and annealing of radiation-induced defects that occur under low-temperature (at 77 K) irradiation (with an energy E > 0.1 MeV) of V−4Ti−4Cr and V−10Ti−5Cr bcc alloys both nonmodified and modified with hydrogen isotopes in a concentration of 200 ppm, as well as the effect of these processes on the physicomechanical properties of these alloys, have been studied. It has been found that the saturation of these alloys with hydrogen leads to slight changes in their strength and ductility characteristics. The irradiation of the alloys at the temperature of 77 K results in a substantial increase in their yield stress and ultimate strength, as well as a decrease in their ductility. In the course of the postradiation annealing of the alloys at a temperature of 130 K, the stage related to the migration of interstitial atoms is observed. At temperatures of 290–320 K, the recovery stage occurs due to the formation of vacancy clusters. The stage that occurs at a temperature of 470 K can be attributed to the formation of impurity-vacancy clusters. Possible mechanisms of the radiation-induced strengthening of the alloys during irradiation and subsequent annealing have been discussed.
Об авторах
V. Arbuzov
Institute of Metal Physics, Ural Branch
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
B. Goshchitskii
Institute of Metal Physics, Ural Branch
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
V. Sagaradze
Institute of Metal Physics, Ural Branch
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
S. Danilov
Institute of Metal Physics, Ural Branch
Автор, ответственный за переписку.
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
Yu. Zuev
Russian Federal Nuclear Center—Zababakhin All-Russian Scientific Research Institute of Technical Physics
Email: danilov@imp.uran.ru
Россия, ul. Vasil’eva 13, Snezhinsk, Chalyabinskaya oblast, 456770
A. Kar’kin
Institute of Metal Physics, Ural Branch
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
V. Parkhomenko
Institute of Metal Physics, Ural Branch
Email: danilov@imp.uran.ru
Россия, ul. S. Kovalevskoi 18, Ekaterinburg, 620990
A. Kozlov
OAO Institute for Reactor Materials
Email: danilov@imp.uran.ru
Россия, Zarechnyi, Sverdlovskaya oblast, 624250
V. Chernov
Bochvar All-Russian Research Institute for Inorganic Materials
Email: danilov@imp.uran.ru
Россия, ul. Rogova 5a, Moscow, 123098
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