Zobrazeno 1 - 10
of 827
pro vyhledávání: '"Plasma-facing materials"'
Autor:
Wei Zheng, Rong Yan, Rui Ding, Guoliang Xu, Lei Mu, Yefan Zhu, Yuming Liu, Junlin Wan, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101828- (2024)
Plasma-wall interaction (PWI) is a critical concern in tokamaks because of its significant impact on the lifetimes of plasma-facing materials (PFMs), fuel retention, and plasma performance. In 2020, the Experimental Advanced Superconducting Tokamak (
Externí odkaz:
https://doaj.org/article/84a4899070cd450da62fa47489536f87
Experimental study on metallic impurity behavior with boronization wall conditioning in EAST tokamak
Autor:
Yunxin Cheng, Ling Zhang, Ailan Hu, Shigeru Morita, Wenmin Zhang, Chengxi Zhou, Darío Mitnik, Fengling Zhang, Jiuyang Ma, Zhengwei Li, Yiming Cao, Haiqing Liu
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101744- (2024)
Operation of EAST tokamak with full metal wall without any wall conditioning are attempted in 2023 and 2024 experimental campaign to address the issues related to ITER tungsten wall operation. It is found that H-mode plasma could be sustained even wi
Externí odkaz:
https://doaj.org/article/beb387c58ba44445ab67869a67245829
Publikováno v:
Fenmo yejin jishu, Vol 42, Iss 3, Pp 242-254 (2024)
During the operation of nuclear fusion reactors, the plasma facing tungsten-based materials need to withstand a certain number of steady-state and transient thermal loads without cracking, melting, and other damage. It is very important to improve th
Externí odkaz:
https://doaj.org/article/60ea66b3c98c49e78be6d4c851f46267
Publikováno v:
Journal of Materials Research and Technology, Vol 30, Iss , Pp 3663-3674 (2024)
The leading design for plasma-facing high heat flux components in proposed fusion reactors involves joining plasma-facing tungsten tiles to underlying reduced activation ferritic-martensitic (RAFM) steel structures. Due to significant differences in
Externí odkaz:
https://doaj.org/article/8084767d3b434830b73790c3f76a8637
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1490-1500 (2024)
Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage leve
Externí odkaz:
https://doaj.org/article/abf874ff2cba4a8da766d2bb2252ac93
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101704- (2024)
Isolated tungsten nanocolumns (W-NCs) have been reported to exhibit a higher radiation resistance than coarse grained W samples, under radiation conditions similar to those that plasma facing materials would face in both magnetic and inertial confine
Externí odkaz:
https://doaj.org/article/7887f3cbbead400cb6cee8cc42d5f66a
Publikováno v:
Metals, Vol 14, Iss 10, p 1197 (2024)
Tungsten (W) and tungsten alloys are being considered as leading candidates for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for the design of magnetic and inertial fusion energy reac
Externí odkaz:
https://doaj.org/article/8ef2da4c5bca4871b083485a3ab91ae7
Autor:
Yu-Wei You, Jinwei Xuan, Kui Hou, Li Wang, Rong Yan, Dongdong Li, X.S. Kong, Xuebang Wu, C.S. Liu
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101636- (2024)
Titanium carbide (TiC), tantalum carbide (TaC) and zirconium carbide (ZrC) in form of particles are widely added in W to improve its mechanical and anti-irradiation properties. However, TiC, TaC and ZrC particles are decomposed to Ti-C-O, Ta-C-O and
Externí odkaz:
https://doaj.org/article/5a999592f970459f9449981896d010b6
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101632- (2024)
The liquid Li coating on the plasma-facing materials (PFM) has been suggested and implemented as a viable and efficient solution to overcome the damage of plasma on PFM in Tokamak devices. However, the internal mechanisms and impacts of tungsten-base
Externí odkaz:
https://doaj.org/article/39be372969464be4bbc2ce7f6ea03a70
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101609- (2024)
Tungsten (W) stands out as a highly promising plasma-facing materials (PFMs) for future nuclear fusion reactors due to its advantages of excellent high temperature strength, low tritium retention and high recrystallization temperature (RCT). Notably,
Externí odkaz:
https://doaj.org/article/2b84a5ebcffc4bdabc3533bdf3e54a48