Results 31 to 40 of about 1,196 (172)

Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR

AIP Advances, 2023
The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience.
Jie Li, Hang Li, Muquan Wu, Xiang Zhu, Peiguang Yan, Xiaodong Lin, Jie Zhang, Xiang Gao   +7 more
doaj   +1 more source

Design and Analysis of the Inlet Valve for the CFETR Torus Cryopump

Energies, 2023
The China Fusion Engineering Test Reactor (CFETR), a superconducting magnetic confinement tokamak fusion reactor, will develop a high-performance torus cryopump to pump torus plasma exhaust gas.
Yaqi Zhou, Hansheng Feng, Shuo Zhang, Ming Zhuang, Ziyu Zhao   +4 more
doaj   +1 more source

A Water Loop Design for the CRAFT Project towards the Testing of CFETR Water-Cooled Blanket and Divertor

Energies, 2021
As one of the tasks of the Comprehensive Research Facility for Fusion Technology (CRAFT), a High Heat Flux (HHF) testing device will be built to test the blanket and divertor of Chinese Fusion Engineering Testing Reactor (CFETR).
Xiaoman Cheng, Zihan Liu, Songlin Liu, Changhong Peng, Wenjia Wang, Qixin Ling   +5 more
doaj   +1 more source

Analyses and optimization of the CFETR power conversion system with a new supercritical CO2 Brayton cycle

Nuclear Fusion, 2023
In this paper, the Chinese Fusion Engineering Testing Reactor (CFETR) power conversion system, with a supercritical CO _2 (SCO _2 ) Brayton cycle, is designed, analyzed and optimized.
Pinghui Zhao, Zhansheng Chen, Yixuan Jin, Teng Wan, Xiaohu Wang, Ke Liu, Mingzhun Lei, Yuanjie Li, Changhong Peng   +8 more
doaj   +1 more source

Tritium supply and use: a key issue for the development of nuclear fusion energy [PDF]

, 2018
Full power operation of the International Thermonuclear Experimental Reactor (ITER) has been delayed and will now begin in 2035. Delays to the ITER schedule may affect the availability of tritium for subsequent fusion devices, as the global CANDU-type ...
Armando B. Antoniazzi, Babutzka, Bell, Canadian Nuclear Association, Canadian Nuclear Safety Commission, Dinner, Federici, Fong, Glugla, Han, Heung, Horton, Klein, Konishi, Kovari, Kovari, Kuan, Kwon, Laberge, Lee, Lopes Cardozo, Menard, Ni, Pearson, Power, Richard J. Pearson, Sawan, Son, Sorbom, Stefan, Sykes, The Hindu, The Telegraph, William J. Nuttall, Willms, World Nuclear Association, World Nuclear Association, World Nuclear Association, Zheng   +38 more
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Heat Transfer Analysis of MgB₂ Coil in Heat Treatment Process for Future Fusion Reactor [PDF]

, 2023
State of the art MgB2 is reviewed as a potential material for the poloidal field (PF) coils of the future fusion reactor due to its high critical temperature and low material cost.
Gao, Peng, He, Yuxiang, Nijhuis, Arend, Qin, Jinggang, Wang, Weijun, Wu, Yongsheng   +5 more
core   +1 more source

Parametric study of helicon wave current drive in CFETR

Nuclear Fusion, 2023
This paper evaluates the feasibility of helicon current drive (HCD) in a hybrid scenario for the China Fusion Engineering Test Reactor (CFETR). Utilizing the GENRAY/CQL3D package, a large number of simulations (over 5000) were conducted, with parametric ...
Xianshu Wu, Jingchun Li, Jiale Chen, Guosheng Xu, Jiaqi Dong, Zhanhui Wang, Aiping Sun, Wulv Zhong   +7 more
doaj   +1 more source

Solid by-products of a CF3I-CO2 insulating gas mixtures on electrodes after lightning impulse breakdown [PDF]

, 2017
This paper investigates the solid by-products of CF3I–CO2 gas mixtures and their proposed use as an alternative insulation medium in gas insulated switchgear and lines.
Haddad, Abderrahmane, Widger, Phillip
core   +1 more source

Research on mechanical properties of high-performance cable-in-conduit conductors with different design [PDF]

, 2020
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak fusion reactor under preliminary design, where the toroidal field (TF) coil has been designed to create a magnetic field of over 14.3 T. The TF conductors need to operate stably at 14.3 T,
Dai, Chao, Devred, Arnaud, Guo, Zichuan, Huang, Chuanjun, Li, Jiangang, Li, Laifeng, Liu, Fang, Nijhuis, Arend, Qin, Jinggang, Xue, Tianjun, Yang, Dongsheng, Yu, Wu, Zhang, Hengcheng, Zhou, Chao   +13 more
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Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR

Theoretical and Applied Mechanics Letters, 2019
: The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP).
Songlin Liu, Xiaoman Cheng, Xuebin Ma, Lei Chen, Kecheng Jiang, Xia Li, Hui Bao, Jichao Wang, Wanjing Wang, Changhong Peng, Peng Lu, Min Li, Kai Huang   +12 more
doaj   +1 more source