Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Yury N. Osetskiy"'
Autor:
Kurt A. Terrani, David T. Hoelzer, Steven J. Zinkle, Kinga A. Unocic, Baptiste Gault, Caleb P. Massey, Philip D. Edmondson, Yury N. Osetskiy
Publikováno v:
Acta Materialia. 200:922-931
Nano-oxide precipitates in a modern nanostructured ferritic alloy were investigated after extreme thermomechanical processing into a thin-walled tube geometry. It was found that the morphology of the precipitates changed from spherical to rod-shaped,
Autor:
Brian D. Wirth, Sergei L. Dudarev, Enrique Martínez, Michael P. Short, Wahyu Setyawan, Daniel R. Mason, Shenyang Y. Hu, Tomohito Tsuru, Tomoaki Suzudo, M.J. Caturla, Yanwen Zhang, Emmanuelle A. Marquis, Steven J. Zinkle, Pär Olsson, David J. Senor, Mihai-Cosmin Marinica, Jason R. Trelewicz, R.J. Kurtz, Fei Gao, Gary S. Was, Z.J. Bergstrom, Xunxiang Hu, Andrey Litnovsky, Kazuto Arakawa, Li Yang, Yury N. Osetskiy, Mark R. Gilbert, Alexandra Goryaeva, Ba Nghiep Nguyen, Jaime Marian
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 554, pp.153113. ⟨10.1016/j.jnucmat.2021.153113⟩
Journal of Nuclear Materials, 2021, 554, pp.153113. ⟨10.1016/j.jnucmat.2021.153113⟩
RUA. Repositorio Institucional de la Universidad de Alicante
Universidad de Alicante (UA)
Journal of Nuclear Materials, Elsevier, 2021, 554, pp.153113. ⟨10.1016/j.jnucmat.2021.153113⟩
Journal of Nuclear Materials, 2021, 554, pp.153113. ⟨10.1016/j.jnucmat.2021.153113⟩
RUA. Repositorio Institucional de la Universidad de Alicante
Universidad de Alicante (UA)
Prediction of material performance in fusion reactor environments relies on computational modelling, and will continue to do so until the first generation of fusion power plants come on line and allow long-term behaviour to be observed. In the meanti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a60b3c85bbc3238f97f3ed9cb808bf9b
https://hal-cea.archives-ouvertes.fr/cea-03292446/file/Workshop_Walla_Walla.pdf
https://hal-cea.archives-ouvertes.fr/cea-03292446/file/Workshop_Walla_Walla.pdf
Autor:
Yongqiang Wang, Shijun Zhao, Yanwen Zhang, Ke Jin, Yury N. Osetskiy, Di Chen, Zhe Fan, Karren L. More, Hongbin Bei
Publikováno v:
Acta Materialia. 164:283-292
Binary single-phase concentrated solid solution alloys (SP CSAs), including Ni80Co20, Ni80Fe20, Ni80Cr20, Ni80Pd20, and Ni80Mn20 (in atomic percentage), were irradiated with 200 keV He+ ions at 500 °C. He cavity size and density distribution were sy
Analysis of experimental result on microstructure evolution in irradiated Zr and alloys has demonstrated that available knowledge on self-interstitial defects in Zr is in contradiction. We therefore have initiated an extensive theoretical and modelin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fc6bf8311a88d3b3a86c96bde3cf6c17
https://doi.org/10.2172/1048714
https://doi.org/10.2172/1048714
Publikováno v:
MRS Proceedings. 1298
In the fusion irradiation environment, helium created by transmutation will play an important role in the response of structural materials to neutron radiation damage. Recently we have developed a new 3-body potential to describe the Fe–He interact