Zobrazeno 1 - 10
of 873
pro vyhledávání: '"dislocation loop"'
Publikováno v:
Yuanzineng kexue jishu, Vol 8, Iss 58, Pp 1662-1670 (2024)
The FeNiCr alloys hold application potential in advanced reactors, however, irradiation hardening severely impacts their safety during service. To further enhance the irradiation hardening theory of the FeNiCr alloys, the interaction mechanism betwee
Externí odkaz:
https://doaj.org/article/2445cb6635bb4e269cbe83a0e0c96039
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3129-3138 (2024)
The in-situ TEM irradiation experiments of zirconium alloy were conducted at 573 K, 673 K, and 773 K utilizing a 400 keV Kr + single beam and a 400 keV Kr+ and 30 keV He + dual beam. The results show that a large number of dislocation loops have been
Externí odkaz:
https://doaj.org/article/f1d6ee82b31345a882ccd2bc8dc07248
Publikováno v:
Scientific Reports, Vol 14, Iss 1, Pp 1-13 (2024)
Abstract Both irradiation and dislocations have been proposed as routes to rationally manipulate spatial distribution and micromorphology of precipitate. An interesting effect emerges in Fe–10at.%Cu–3at.%Mn–1.5at.%Ni–1.5at.%Al alloy due to th
Externí odkaz:
https://doaj.org/article/7cf11a1dfbe94e2f891487b46803538a
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2282-2291 (2024)
In this work we study the effects of different factors of dislocation loop on its obstacle strength when interacting with an edge dislocation. At first, the interaction model for dislocation and dislocation loop is established and the full and partia
Externí odkaz:
https://doaj.org/article/45f1c5cc2c694b5a82113834768bc544
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101729- (2024)
Bulk W-0.5 wt%ZrC (W-ZrC), W-1 wt%Re-0.5 wt%ZrC (W-1Re-ZrC), and W-3 wt%Re-0.5 wt%ZrC (W-3Re-ZrC) alloys were prepared and exposed to He2+ ion irradiation with an incident energy of 500 keV at 400 °C. Post-irradiation analysis revealed the formation
Externí odkaz:
https://doaj.org/article/6f3c9bf629ef4015a5fa4caafb8e45d7
Autor:
Li, Jie a, b, Zhu, Yaxin a, b, Zhao, Lv a, b, Liang, Shuang a, b, Huang, Minsheng a, b, ⁎, Li, Zhenhuan a, b, ⁎
Publikováno v:
In Journal of Alloys and Compounds 15 October 2024 1002
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 8, Pp 1614-1624 (2023)
After neutron irradiation, RAFM steel will produce two types of interstitial dislocation loops (1/2〈111〉 loop and 〈100〉 loop), resulting in radiation hardening and embrittlement after long service. And different types of dislocation loops may
Externí odkaz:
https://doaj.org/article/dc02e09f61df4d008472098c3311deed
Autor:
Nguyen Ba Vu Chinh, Kenta Murakami, Liang Chen, Phongsakorn Prak Tom, Xinrun Chen, Takashi Hashimoto, Taehyun Hwang, Akinori Furusawa, Tatsuya Suzuki
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101639- (2024)
In reactor pressure vessel materials, the formation of Mn- and Ni-rich nanoclusters is a major cause of neutron irradiation embrittlement. The segregation of these solute atoms into dislocation loops has attracted attention as a mechanism to accelera
Externí odkaz:
https://doaj.org/article/2d9dfd8ce33f4229aa8bf45f4c221c2f
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Akademický článek
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