Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Yaxia Wei"'
Autor:
Yinshu Zhao, Pengfei Zheng, Yaxia Wei, Hongtai Luo, Wei Qian, Guihang Zhang, Feng Li, Ming Zhang, Pengbo Zhang
Publikováno v:
Metals, Vol 14, Iss 2, p 141 (2024)
V-4Cr-4Ti alloy is one of the candidate structural materials for future fusion reactors due to its desirable characteristics. In our previous research, MAX-phase-dispersion-strengthened vanadium alloy (V-4Cr-4Ti-1.5Y-0.3Ti3SiC2), prepared through mec
Externí odkaz:
https://doaj.org/article/dcb5f397ca8749c590588623ee00a400
Autor:
Shuo Liu, Yaxia Wei, Yuanrong Lu, Zhi Wang, Meiyun Han, Tianhao Wei, Yin Xia, Haipeng Li, Shuli Gao, Pengfei Zheng
Publikováno v:
Applied Sciences, Vol 12, Iss 8, p 4031 (2022)
In order to figure out the migration and deposition of impurities on the first wall of HL-2A/2M tokamak, Peking University and Southwestern Institute of Physics are co-developing a deuteron RFQ as part of the in situ ion-beam diagnostic for the mater
Externí odkaz:
https://doaj.org/article/c45305b25ba042f0ac5fdccce513c2eb
Autor:
Xiong Zhou, Liping Guo, Yaxia Wei, Hui Wang, Cheng Chen, Yiheng Chen, Weiping Zhang, Shi Liu, Renduo Liu, Shaobo Mo
Publikováno v:
Nuclear Materials and Energy, Vol 21, Iss , Pp - (2019)
Five kinds of iron-chromium-aluminum (FeCrAl) alloy samples with different contents of aluminum (Al)—Fe-12Cr, Fe-12Cr-2Al, Fe-12Cr-4Al, Fe-12Cr-6Al, and Fe-12Cr-8Al—were designed and prepared. All samples were then irradiated with 200 keV argon i
Externí odkaz:
https://doaj.org/article/85a51d3cb75346f68205593a5ee3f675
Publikováno v:
Metals, Vol 9, Iss 7, p 735 (2019)
Under irradiations, mechanical performance of nuclear alloys would degrade due to irradiation induced defects. Different strengthening methods can play a different role in the evolution of the defects. In this study, the effect of four typical streng
Externí odkaz:
https://doaj.org/article/f3057fe9ae1a4a0c978777010051c63e
Autor:
Weiping Zhang, Liping Guo, Zhenyu Shen, Jingping Xin, Qunying Huang, Yaxia Wei, Yunxiang Long, Xiong Zhou, Cheng Chen
Publikováno v:
Materials, Vol 11, Iss 11, p 2276 (2018)
Hydrogen can be induced in various ways into reduced-activation ferritic/martensitic (RAFM) steels when they are used as structural materials for advanced nuclear systems. However, because of the fast diffusion of hydrogen in metals, the effect of hy
Externí odkaz:
https://doaj.org/article/1a7b2ee058e8421d873462fe5065896b
Publikováno v:
Materials, Vol 11, Iss 9, p 1523 (2018)
The behavior of helium in reduced-activation ferritic/martensitic steels was investigated systematically with positron annihilation Doppler broadening measurement and thermal desorption spectroscopy. Specimens were irradiated with helium ions with di
Externí odkaz:
https://doaj.org/article/93a0648b6d3c48f198fe76ba1d88a288
Publikováno v:
Journal of Nuclear Materials. 574:154160
Autor:
Fang Li, Liping Guo, Yiheng Chen, Yunxiang Long, Yaxia Wei, Ziyang Xie, Hongtai Luo, Wenbin Lin, zhangjian zhou, Hui Wang
Publikováno v:
SSRN Electronic Journal.
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 461:83-87
The effect of the concentration of hydrogen (H) atoms on the hydrogen diffusion and evolution of hydrogen bubbles in body-centered cubic iron was investigated using molecular statics and molecular dynamics methods. The simulation results indicate tha