Zobrazeno 1 - 10
of 10 652
pro vyhledávání: '"zirconium alloy"'
Publikováno v:
He huaxue yu fangshe huaxue, Vol 46, Iss 5, Pp 450-461 (2024)
Uranium-zirconium alloy is an important nuclear fuel in Integral Fast Reactor, which is of great significance to study its basic physical properties at high temperature by using advanced calculation methods. This work used deep potential molecular dy
Externí odkaz:
https://doaj.org/article/a29bcbf5b6c640ae8b2de91a7f99fb97
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1950-1957 (2024)
The corrosion resistance of zirconium alloy is of great relevance to the long-term operation of reactors. The surface of zirconium alloy undergoes oxidation in the complex environment of nuclear reactors, and their weight increases gradually. In orde
Externí odkaz:
https://doaj.org/article/c2cd22f38855447e8101aae22bce5dce
Autor:
Nan Li, Liang-Yu Chen, Linjiang Chai, Hao-Nan Xuan, Zexin Wang, Lina Zhang, Dubovyy Oleksandr, Jun Zhang, Sheng Lu
Publikováno v:
Journal of Materials Research and Technology, Vol 30, Iss , Pp 5569-5581 (2024)
To better meet the requirements in loss-of-coolant accidents (LOCA) and conventional operating conditions in nuclear applications, this work prepared Cr, FeCrAl, and Cr/FeCrAl composite coatings on Zr alloys using plasma spraying technology. The micr
Externí odkaz:
https://doaj.org/article/8be54bfeec2d4646ae23c0f9d363622d
Autor:
Aditi Verma, Kaushal Kishor Agrawal, Pooran Chand, Ramashanker, Shuchi Tripathi, Deeksha Arya
Publikováno v:
Indian Journal of Dental Research, Vol 34, Iss 4, Pp 365-370 (2024)
Background: Studies comparing the clinical performance of titanium zirconium (Ti-Zr) and titanium (Ti) dental implants subjected to immediate loading in the posterior mandibular region where occlusal forces are higher are sparse in the current litera
Externí odkaz:
https://doaj.org/article/10646f6c1afd465d9d255a4779ff9f50
Publikováno v:
Journal of Materials Research and Technology, Vol 29, Iss , Pp 2799-2806 (2024)
A comparison was conducted on the microstructure, mechanical properties, and corrosion resistance of the fusion zone (FZ) in Zr R60702 laser lap joints prepared under air-cooled and water-cooled conditions. The results reveal that the upper and lower
Externí odkaz:
https://doaj.org/article/6e1312240aca4db8ab5a9729a63a10b7
Publikováno v:
Journal of Hebei University of Science and Technology, Vol 45, Iss 1, Pp 1-14 (2024)
Zirconium alloys are widely used as structural materials in civil power reactors, nuclear-powered aircraft carriers, nuclear submarines and space vehicles as well as medical materials due to their excellent nuclear properties and biocompatibility. Zi
Externí odkaz:
https://doaj.org/article/0870b9b59a3746ca80e488caa0291425
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 1, Pp 149-156 (2024)
The zirconium alloy cladding of PWR fuel rods which undergo high neutron irradiation during service, will cause significant changes in its microstructure, thereby affecting its macroscopic performance. Therefore, the study of neutron irradiation beha
Externí odkaz:
https://doaj.org/article/2576309bf745469eb4f417f6450d0f8c
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 1, Pp 175-180 (2024)
The diffusion coefficient of oxygen in zirconium alloy oxide film and matrix is an important parameter in corrosion kinetics of zirconium alloys. At present, there are some reports on the diffusion coefficient of oxygen in zirconium and oxide film, b
Externí odkaz:
https://doaj.org/article/dc12f7951a1341a6a910d1915617e635
Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review
Publikováno v:
Frontiers in Materials, Vol 11 (2024)
Operated under extreme conditions, corrosion occurs between zirconium alloy cladding tubes and the coolant in the primary loop of pressurized water reactors (PWRs), contributing to a reduction in the effective metallic material thickness. Therefore,
Externí odkaz:
https://doaj.org/article/5ee5e36b05c54668b700e0e378596811
Autor:
Gang Feng, Jian Lin, Shuai Yang, Boxuan Zhang, Jiangang Wang, Jia Yang, Zhongfeng Xu, Yongping Lei
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4066-4076 (2023)
Pressure resistance welding is usually used to seal the connection between the cladding tube and the end plug made of zirconium alloy. The seal welded joint has a direct effect on the service performance of the fuel rod cladding structure. In this pa
Externí odkaz:
https://doaj.org/article/48cd6538ab574d9b9e4a1b979ba9d685