Zobrazeno 1 - 10
of 239
pro vyhledávání: '"He Xinfu"'
In body-centered cubic (bcc) metals such as molybdenum, screw dislocations often exhibit non-Schmid behavior, moving in directions unpredicted by the Schmid law. The mobility of these dislocations is notably influenced by the presence of solute atoms
Externí odkaz:
http://arxiv.org/abs/2404.04897
Development and Validation of Radiation Embrittlement Prediction Model of Austenitic Stainless Steel
Publikováno v:
Yuanzineng kexue jishu, Vol 8, Iss 58, Pp 1635-1645 (2024)
Austenitic stainless steels are used as important structural materials in nuclear reactors due to their high fracture toughness. In the process of long-term service, austenitic stainless steel will be subjected to neutron irradiation to cause microst
Externí odkaz:
https://doaj.org/article/8e193a4703124feea15f018e91444b78
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:
Yuanzineng kexue jishu, Vol 58, Iss S1, Pp 110-120 (2024)
Grain boundaries are important microstructures in metallic materials, and dislocation nucleation on grain boundaries plays a crucial role in material deformation. Studies on P segregation on grain boundaries typically focus on segregation behavior at
Externí odkaz:
https://doaj.org/article/66844532c9b148b5828953c4bedac383
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss S1, Pp 121-130 (2024)
Core structural materials such as cladding in advanced nuclear reactors face harsh service environments such as high-temperature, and their comprehensive performance is one of the bottlenecks restricting the development of advanced reactors. Mo and i
Externí odkaz:
https://doaj.org/article/21c66fd171814732919f7aade61b7f7e
Autor:
Wang, Xudong, Qiu, Rongyang, Dou, Yankun, Chen, Yangchun, Xiang, Haipan, Jiang, Peng, He, Xinfu, Yang, Wen, Liu, Guangdong, Deng, Huiqiu
Publikováno v:
In Nuclear Materials and Energy December 2024 41
Publikováno v:
In Fusion Engineering and Design November 2024 208
Publikováno v:
In Fusion Engineering and Design November 2024 208
Autor:
Shi, Zhiwei, Zhang, Zhi, Han, Huiyu, He, Xinfu, Zhang, Yagang, Zhou, Anning, Jin, Lijun, Hu, Haoquan
Publikováno v:
In Journal of Analytical and Applied Pyrolysis October 2024 183
Autor:
Qiu, Rongyang, Chen, Yangchun, Liao, Xichuan, Dou, Yankun, He, Xinfu, Yang, Wen, Hu, Wangyu, Deng, Huiqiu
Publikováno v:
In Journal of Nuclear Materials October 2024 599