Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Chunyi Xie"'
Autor:
Xingli Wang, Guang-Nan Luo, Wanjing Wang, Qiang Li, Chunyi Xie, Jichao Wang, Qingran Gao, Yuping Xu, Feng Liu, Zhenmao Chen
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 498-502 (2019)
The tungsten divertor of the Experimental Advanced Superconducting Tokamak (EAST) device operates at varying temperatures and strong electromagnetic fields during plasma operation. In order to monitor the thermomechanical and electromagnetic response
Externí odkaz:
https://doaj.org/article/86d084c2d3174b10864e8fa2eff3479c
Autor:
Qiang Li, Zhen Chen, Wuqingliang Peng, Chunyi Xie, Wanjing Wang, Xiang Geng, Fangyong Du, Haishan Zhou, Songlin Liu, G.-N. Luo
Publikováno v:
Fusion Engineering and Design. 183:113276
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::93105eee699a0f21be3bbbe93f1275f4
https://doi.org/10.1016/j.fusengdes.2022.113276
https://doi.org/10.1016/j.fusengdes.2022.113276
Autor:
Wanjing Wang, Jiangang Li, Huibin Sun, Guang-Nan Luo, Ji-Chao Wang, Qiang Li, Songlin Liu, Chunyi Xie, Xiang Gao, Chen Zhen, Jianjun Huang, Xingli Wang, Qingran Gao
Publikováno v:
Fusion Engineering and Design. 138:313-320
The first wall (FW) of a water cooled ceramic breeder (WCCB) blanket uses ferritic/martensitic steel (FMS) as structural material and tungsten (W) as armor material. The FW is exposed to fusion reaction fuels: deuterium (D) or tritium (T) plasma; and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b98e47fd5c696fad7c356df6fec10567
https://doi.org/10.1016/j.fusengdes.2018.12.010
https://doi.org/10.1016/j.fusengdes.2018.12.010
Autor:
T. Hirai, Jichao Wang, Wanjing Wang, Frederic Escourbiac, S. Panayotis, Z. Sun, Chunyi Xie, Qiang Li, Xingli Wang, Ran Wei, Guang-Nan Luo
Publikováno v:
Fusion Engineering and Design. 121:60-69
In 2015, as part of ITER Full-Tungsten Divertor Qualification Program, Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) manufactured six small-scale Tungsten (W) monoblock mock-ups that were tested at the electron beam facility, ITER D
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c65573daaf5b21a2971c94146788910
https://doi.org/10.1016/j.fusengdes.2017.06.009
https://doi.org/10.1016/j.fusengdes.2017.06.009
Publikováno v:
Journal of Nuclear Materials. 485:8-14
Tungsten (W) and steel bonding is one of the key technologies for blanket First Wall (FW) manufacture in thermal fusion reactor. The W/Steel joints are prone to fail without interlayer for the different thermo physical properties. To study the effect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a0155bf24f888aabb52ef0f666217c5e
https://doi.org/10.1016/j.jnucmat.2016.12.024
https://doi.org/10.1016/j.jnucmat.2016.12.024
Publikováno v:
Fusion Engineering and Design. 112:67-73
W and P91 steel were joined by using the Hot Isostatic Pressing method with Ti interlayer, and the experiments were conducted at 760 °C. The mechanical property, bonding quality and interface microstructure were tested by the Torsion test, Non-Destr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::aeac1d09a83257171b78003e43c8ae2c
https://doi.org/10.1016/j.fusengdes.2016.07.012
https://doi.org/10.1016/j.fusengdes.2016.07.012
Autor:
Chunyi Xie, Shiwei Xu, Guang-Nan Luo, Wanjing Wang, Sigui Qin, Guohui Liu, Qiang Li, Jichao Wang, Mingzhun Lei, Songlin Liu
Publikováno v:
Fusion Engineering and Design. 159:111758
As one candidate of blankets for China Fusion Engineering Test Reactor (CFETR), the Water Cooled Ceramic Breeder (WCCB) blanket is proposed and designed in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). Supported by the National Ke
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43b86d08ce69a3eecf29c68f5f3c8c44
https://doi.org/10.1016/j.fusengdes.2020.111758
https://doi.org/10.1016/j.fusengdes.2020.111758
Publikováno v:
Light, Energy and the Environment 2018 (E2, FTS, HISE, SOLAR, SSL).
FBG has been applied to fusion field and used to monitor surface strain and temperature of tokamak tungsten divertor component under baking and high heat flux tests, respectively. This is a summary of the works.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ff0a97b55d3aef30506434f27df9d9ae
https://doi.org/10.1364/ee.2018.et5a.6
https://doi.org/10.1364/ee.2018.et5a.6
Autor:
Jing Wu, Xianzu Gong, P.C. Stangeby, William R. Wampler, G.-N. Luo, Andrey Litnovsky, Rui Ding, R.A. Pitts, Hai-Shan Zhou, Fang Ding, M. Fukumoto, Chen Liang, M. Hellwig, Naoko Ashikawa, Sophie Carpentier, Huiqian Wang, Wenzhang Wang, Hongmin Mao, Songlin Liu, Rong Yan, Kazunari Katayama, Junling Chen, Chunyi Xie
Publikováno v:
Journal of Nuclear Materials. 455:710-716
The Material and Plasma Evaluation System (MAPES) in the EAST tokamak has been built up and used to address a variety of plasma–material interaction (PMI) issues relevant to ITER in 2012 EAST campaign. The topics studied cover erosion/redeposition
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::da917270d9bcd7df7c90b451608ff401
https://doi.org/10.1016/j.jnucmat.2014.09.017
https://doi.org/10.1016/j.jnucmat.2014.09.017
Autor:
Chunyi Xie, Wuqingliang Peng, Xingli Wang, Qingran Gao, G.-N. Luo, Wanjing Wang, Zhongshi Yang, Qiang Li, Jichao Wang, Chen Zhen
Publikováno v:
Fusion Engineering and Design. 147:111262
Thanks to its excellent heat removal capability, good performance under high heat flux (HHF) test and higher critical heat flux (CHF) value, the water cooled monoblock type plasma facing component (PFC) will be the optimal choice for divertor targets
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7655c9dbef14b2f7f99aa033fecd6757
https://doi.org/10.1016/j.fusengdes.2019.111262
https://doi.org/10.1016/j.fusengdes.2019.111262