Zobrazeno 1 - 10
of 51
pro vyhledávání: '"Xiaoou Yi"'
Autor:
Fengcheng Liu, Hucheng Yu, Xiaoou Yi, Shunjie Deng, Shulei Li, Kiyohiro Yabuuchi, Somei Ohnuki
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101627- (2024)
γ-Al2O3/FeAl coatings for tritium permeation barrier (TPB) application in fusion reactors were fabricated via electro-chemical deposition and selective oxidation. The TPB coatings consisted of a γ-Al2O3 scale (200 nm), an upper interlayer of FeAl (
Externí odkaz:
https://doaj.org/article/da10d34e7ed3411982fdc8a903e120d8
Publikováno v:
Journal of Materials Research and Technology, Vol 27, Iss , Pp 4738-4749 (2023)
The effect of non-isothermal creep aging (NICA) on the microstructure, mechanical properties, and stress corrosion cracking (SCC) resistance of 7075 alloy was investigated. The results showed that the tensile strength of the alloy increased to 565 MP
Externí odkaz:
https://doaj.org/article/c446f8e8885749a68a5b2a0e302b05f1
Autor:
Lei Zhang, Yufeng Du, Wentuo Han, Xiaoou Yi, Pingping Liu, Kenta Yoshida, Takeshi Toyama, Chi Xu, Qian Zhan, Yasuyoshi Nagai, Somei Ohnuki, Farong Wan
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101432- (2023)
Due to the expression of “reduced activation”, the severe radioactivity of tantalum (Ta) after neutron irradiation in early decay years is easily neglected. In the presented study, after an irradiation of only 0.3 dpa by fission neutron and follo
Externí odkaz:
https://doaj.org/article/f2e7c1b909ad43e5a578ceddc2b9418e
Autor:
Lei Zhang, Yufeng Du, Wentuo Han, Pingping Liu, Xiaoou Yi, Kiyohiro Yabuuchi, Somei Ohnuki, Farong Wan
Publikováno v:
Nuclear Materials and Energy, Vol 29, Iss , Pp 101056- (2021)
Grain boundary plays an important role in irradiation damage. The presented work proposes an approximate in-situ method, mesh-covered ion irradiation (MCII) for investigating the irradiation damage. The method was applied to a Fe-9 wt.% Al model allo
Externí odkaz:
https://doaj.org/article/82b4cff40b7146dc8ebd40ca36722fba
Autor:
Xiaoou Yi, Kazuto Arakawa, Yufeng Du, Francesco Ferroni, Wentuo Han, Pingping Liu, Farong Wan
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 93-98 (2019)
A study of high-temperature defect recovery has been carried out for W-5 wt% Ta alloy, irradiated with 2 MeV W+ ions at 500 °C, up to 1.2 dpa. After post-irradiation annealing at 1200 °C for 15 min, the damage microstructure evolved from a random d
Externí odkaz:
https://doaj.org/article/ea4dd6cda0ce4a2195e38d40d9b8474d
Publikováno v:
Nuclear Materials and Energy, Vol 13, Iss C, Pp 99-103 (2017)
Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder (HCCB) test blanket module (TBM), which is the primary option of the Chinese TBM program. The characteristic of the microstructural change of beryllium under
Externí odkaz:
https://doaj.org/article/f1a5112456af4cc8952eacc2354fa6c7
Publikováno v:
Applied Sciences, Vol 8, Iss 4, p 577 (2018)
Diffusion bonding of V–4Cr–4Ti alloy to pure titanium (Ti) was carried out by hot forging in the temperature range between 1150 °C and 950 °C. The microstructure and mechanical properties of the bonded joint were determined by using light optic
Externí odkaz:
https://doaj.org/article/b4a3fd4be60344d38a1da805c0ef7fef
Autor:
Shiwei Wang, Wangguo Guo, Hanqing Wang, Xiaoou Yi, Lin Ge, Yuhan Sun, Long Cheng, Xiaona Zhang, Yue Yuan, Xingzhong Cao, Engang Fu, Guang-Hong Lu
Publikováno v:
Journal of Nuclear Materials. 581:154454
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4f0789f8f1ca01995e80ca6db5aa0ac0
https://doi.org/10.1016/j.jnucmat.2023.154454
https://doi.org/10.1016/j.jnucmat.2023.154454