Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Zongxiao Guo"'
Autor:
Wenxue Fu, Dahuan Zhu, Binfu Gao, Zongxiao Guo, Bin Zhang, Mehdi Firdaouss, Chuannan Xuan, Rong Yan, Yang Wang, Chunyu He, Yi Li, Baoguo Wang, Rui Ding, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101759- (2024)
In tokamak devices, the performance of plasma facing components (PFCs) under high heat loads is a key challenge for achieving long-pulse and high-performance plasma operations. The lower divertor of EAST adopts an ITER-like cassette modules (CMs) str
Externí odkaz:
https://doaj.org/article/46a41375c4e043f883ac777f12fc8b61
Autor:
Yang Wang, Dahuan Zhu, Chuannan Xuan, Zongxiao Guo, Chunyu He, Binfu Gao, Baoguo Wang, Rui Ding, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101665- (2024)
W/Cu monoblocks will be employed in ITER as divertor targets for high heat loads. Experimental results of W/Cu monoblocks in high heat flux (HHF) tests have demonstrated their endurance on 5000 cycles at 10 MW/m2 and occasionally 300 cycles at 20 MW/
Externí odkaz:
https://doaj.org/article/64c1109e0aa74231a4e85d4207c47d3c
Autor:
Zongxiao Guo, Dahuan Zhu, Changjun Li, Baoguo Wang, Rui Ding, Chuannan Xuan, Binfu Gao, Baixue Yu, Yang Wang, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101524- (2023)
EAST is the first tokamak to feature fully actively water-cooled ITER-like W/Cu monoblocks on the divertor target. In 2014 and 2021, the graphite tiles in the upper and lower divertor were upgraded to W/Cu monoblocks, respectively. With the increase
Externí odkaz:
https://doaj.org/article/a48982d5024d43ce9334720800f26641
Autor:
Zongxiao Guo, Baixue Yu, Dahuan Zhu, Chuannan Xuan, Binfu Gao, Changjun Li, Rui Ding, Junling Chen, Chun Du
Publikováno v:
Nuclear Materials and Energy, Vol 36, Iss , Pp 101503- (2023)
Plasma disruption is one of the most dangerous events which will directly influence operation safety of future large-scale fusion devices. During the thermal quench (TQ) stage, extremely high transient heat flux up to thousands of MWm−2 (in several
Externí odkaz:
https://doaj.org/article/5dff8f07f56b470e865e7a13dc87fac6
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101431- (2023)
To study the manufacturing method of the tungsten armored first wall of tokamak devices, the W-316 L steel (W-SS) composite coatings were fabricated on 316 L steel substrates by detonation spraying (DS) as the interlayer of pure tungsten coatings man
Externí odkaz:
https://doaj.org/article/1624dd77d3d1458ca6c9f901842d929b
Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments
Autor:
Zongxiao Guo, Dahuan Zhu, Rong Yan, Chuannan Xuan, Baoguo Wang, Yang Wang, Binfu Gao, Chunyu He, Rui Ding, Yi Li, Wenxue Fu, Junling Chen, the EAST Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 7, p 076026 (2024)
In the ITER and future fusion devices, W/Cu monoblocks will be used as divertor target which are exposed to both steady state heat load and transient heat flux. Especially, the transient heat flux up to 10 GW m ^−2 during plasma disruption, is expe
Externí odkaz:
https://doaj.org/article/3acfff96b41e4a6f8bbcf28ef759174e
Autor:
Chuannan Xuan, Dahuan Zhu, Binfu Gao, Rong Yan, Zongxiao Guo, Rui Ding, Baoguo Wang, Pengfei Zi, Yang Wang, Junling Chen, the EAST Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 8, p 086039 (2024)
A type of actively cooled W/Cu flat-type component with high heat exhaust capacity was installed as limiter during the EAST spring plasma campaign in 2022, aiming to support the long pulse operation. Unfortunately, severe melting phenomena with obvio
Externí odkaz:
https://doaj.org/article/d98704186b4c4a8a805b9bc8ee8f994c
Autor:
Chuannan Xuan, Dahuan Zhu, Changjun Li, Zongxiao Guo, Binfu Gao, Rui Ding, Baoguo Wang, Baixue Yu, Yang Lei, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101377- (2023)
Plasma facing materials (PFMs) are subjected to long-duration high-energy particle streams and radiation in tokamak devices. The PFMs of EAST have been upgraded several times and Titanium-Zirconium-Molybdenum (TZM) tiles were installed into EAST as i
Externí odkaz:
https://doaj.org/article/fed866406c0346eeb5bb0863ea09bb82
Publikováno v:
Nuclear Materials and Energy, Vol 32, Iss , Pp 101227- (2022)
The W/Cu monoblock for divertor target will be exposed to cyclic (∼300 cycles) and extremely high heat flux up to 20 MW/m2 in ITER, which may lead to significant macro cracking and W recrystallization according to existing high heat flux tests. Cur
Externí odkaz:
https://doaj.org/article/9d90016216cf49838af4f7c6126a98aa
Autor:
Deli, Zhou, Xingli, Wang, Zongxiao, Guo, Yang, Liu, Ying, Liu, Weibing, Liao, Chunyan, Yu, Fan, Wang, Jianjun, Huang
Publikováno v:
In Journal of Nuclear Materials February 2024 589