Zobrazeno 1 - 10
of 2 264
pro vyhledávání: '"J.S Hu"'
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101594- (2024)
Liquid lithium (Li) is a candidate material for the first wall and blanket coolants/breeders in fusion devices. Reduced activation ferritic/martensitic (RAFM) steels are also considered primary candidate structural materials for fusion reactors. Thus
Externí odkaz:
https://doaj.org/article/737912637d564770a94ae626e9024b14
Autor:
S.A. Puyang, Y.P. Xu, Y.H. Guan, Z.S. Yang, F. Ding, H.S. Zhou, G.Z. Zuo, J.S Hu, G.-N. Luo, the EAST Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 7, p 074001 (2024)
Effective management of hydrogen isotopes retention in plasma-facing materials (PFMs) is crucial, particularly when utilizing tritium (T) as fuel, for the success of burning plasma operations. Boronization, a widely employed technique for controlling
Externí odkaz:
https://doaj.org/article/5fb8f3c59c8b4aaa8d2d0b13c40d9f8d
Autor:
Y. Zhang, X.J. Wang, F. Hong, W. Zhang, H.D. Xu, T.H. Shi, E.Z. Li, Q. Ma, H.L. Zhao, S.X. Wang, Y.Q. Chu, H.Q. Liu, Y.W. Sun, X.D. Zhang, Q. Yu, J.P. Qian, X.Z. Gong, J.S. Hu, K. Lu, Y.T. Song, the EAST Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 7, p 076016 (2024)
The stabilization of the m / n = 2/1 neoclassical tearing mode (NTM) by electron cyclotron current drive (ECCD) has been carried out in EAST H-mode discharges, where m / n is the poloidal/toroidal mode number. The experimental results are reported fo
Externí odkaz:
https://doaj.org/article/0c94567c1fe54e81b7ba716b9dc9829e
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101407- (2023)
The clean wall condition in tokamak devices can be achieved by utilizing the active chemical property of lithium (Li). This also exposes Li to air contamination even when protected by inert gas. To determine whether air contamination affects the rete
Externí odkaz:
https://doaj.org/article/9ccb74bc67934a0da791665d7e3c17bb
Autor:
K. Wu, Q.P. Yuan, D. Eldon, K.D. Li, Y.M. Duan, L.Y. Meng, L. Wang, H.Q. Wang, J.J. Huang, L. Zhang, Z.P. Luo, X.J. Liu, B. Cao, J.B. Liu, F. Ding, G.S. Xu, J.S. Hu, B.J. Xiao, G. Calabrò, P. Innocente
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101398- (2023)
EAST implements the double feedback control experiments of the detachment by using two control systems at the same time to explore the new detachment control way. We hire two PID controllers and two gas puffing valves dividedly to inject impurity gas
Externí odkaz:
https://doaj.org/article/68d3bda31b944ebd8311359023c4842a
Autor:
W. Xu, Z. Sun, R. Maingi, G.Z. Zuo, Y.W. Yu, C.L. Li, Y.H. Guan, Z.T. Zhou, X.C. Meng, M. Huang, L. Zhang, W. Gao, J.S. Hu
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101359- (2023)
Real-time wall conditioning and edge-localized mode (ELM) suppression through real-time boron powder injection into high-confinement mode discharges of the Experimental Advanced Superconducting Tokamak (EAST) have been investigated. The boron powder
Externí odkaz:
https://doaj.org/article/e8cdd96ed5aa482a823c81125ae6d3fa
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101291- (2022)
Particle control is one of the key issues for steady-state tokamak operation. The density decay time is used to evaluate the capability of the divertor to exhaust particle with all fueling turn off. Experiments of the EAST divertor's ability to exhau
Externí odkaz:
https://doaj.org/article/000efcd0266b49d881c6c8892ab0e5e5
Autor:
G.Z. Zuo, C.L. Li, R. Maingi, X.C. Meng, D. Andruczyk, P.J. Sun, Z. Sun, W. Xu, M. Huang, Z.L. Tang, D.H. Zhang, Y.J. Chen, Q. Zang, Y.M. Wang, Y.F. Wang, K. Tritz, J.S. Hu
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101263- (2022)
Particle and heat fluxes were successfully controlled by using a continuously flowing liquid Li (FLiLi) limiter in the H-mode discharges with high plasma heating power in the Experimental Advanced Superconducting Tokamak device. There were strong int
Externí odkaz:
https://doaj.org/article/6a5b72f3f87a48d78c4c7dc22d35041e
Autor:
J.S. Yuan, G.Z. Zuo, S.B. Zhao, L. Li, H.D. Zhuang, L. Zeng, S.T. Mao, Y.M. Duan, D.L. Chen, L.Q. Xu, J.L. Hou, M. Huang, Y. Chen, J.S. Hu
Publikováno v:
Nuclear Fusion, Vol 63, Iss 10, p 106008 (2023)
Disruption mitigation poses a significant and unresolved challenge for ITER and future fusion reactor devices. To mitigate the effect of plasma disruption, a Shattered Pellet Injection (SPI) system has been developed and the first rapid shutdown expe
Externí odkaz:
https://doaj.org/article/0c6f7a3176f74034957ae69cbe81ccff
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss , Pp 101049- (2021)
Lithium is chemically active and prone to react with residual gases in the atmosphere, which should be taken into account for the application of lithium in fusion facility. In the present study, effect of N2 on the release temperature of D2 in liquid
Externí odkaz:
https://doaj.org/article/afd695ccea394bc3b91e42f094755172