Results 71 to 80 of about 2,258 (214)

Mechanical effects: challenges for high-field superconducting magnets. [PDF]

Natl Sci Rev, 2023
Zhang X, Qin J.
europepmc   +1 more source

High performance of an innovative cable-in-conduit conductor with CWS cable pattern [PDF]

Cable-in-conduit conductors, known as CICCs, were developed for constructing superconducting coils in tokamak fusion reactors. To achieve large currents in high magnetic field, CICCs were utilized with a short-twist-pitch (STP) cable pattern to prevent ...
Dai, Chao, Guo, Zichuan, Liu, Yunhao, Nijhuis, Arend, Qin, Jinggang, Wang, Wei, Zhou, Chao   +6 more
core   +1 more source

Research on motion planning and precision control algorithm of the CFETR multipurpose overload robot [PDF]

In order to handle the complex maintenance tasks of the CFETR’s divertor, a multipurpose overload remote handling robot has been designed by the remote handling team of ASIPP (Institute of Plasma Physics, Chinese Academy of Sciences).
Yao, Zhixin
core  

Steady-state burning plasma: a new stage in the development of magnetic confinement fusion energy. [PDF]

Natl Sci Rev, 2023
Wan B, Xu G.
europepmc   +1 more source

Mode evolution of TAE due to alpha particles and synergy with ripple loss in CFETR

Nuclear Fusion
The alpha particle should have good confinement when there are instabilities and toroidal field ripples in fusion devices. With the alpha particle slowing down distribution generated by TRANSP/NUBEAM, the Alfven eigenfunction calculated by NOVA/NOVA-K ...
B. Hao, Wei Chen, Xiao-Dong Lin, Jiquan Li, G. Hao, Jiale Chen, Bin Wu, Vincent Chan, Wenjun Yang   +8 more
semanticscholar   +1 more source

Research on the optimization method of tritium release efficiency in a water cooled blanket for CFETR

AIP Advances
The Chinese Fusion Engineering Test Reactor (CFETR) is a tokamak device located between ITER and DEMO, with the primary goal of generating useable fusion energy through D–T reactions.
Jie Li, Xianbing Xiang, Xiaoyi Zeng, Haiyan Yang, Jie Zhang   +4 more
doaj   +1 more source

EMC3-EIRENE simulations of edge plasma and impurity transport by toroidally localized argon seeding on CFETR X-divertor

Nuclear Fusion
The three-dimensional (3D) edge Monte Carlo transport code EMC3-EIRENE has been employed to study edge plasma and impurity transport with toroidally localized argon seeding using the Chinese fusion engineering testing reactor (CFETR) X-divertor ...
T. Xie, H. Li, W. Zhang, R. Ding, L. Wang, Y. Luo, D.Z. Wang   +6 more
doaj   +1 more source

Mobile electrical lift for lifting heavy load in fusion reactor [PDF]

Nuclear fusion is one way to solve energy shortage problem. DEMO is the abbreviation for the demonstration power plant. Due to the extreme environment inside the DEMO, the maintenance of main parts after shutdown of devices cannot be processed by ...
Jian, Cui
core  

Plastic deformation in advanced tungsten-based alloys for fusion applications studied by mechanical testing and TEM [PDF]

, 2020
Antusch, Steffen, Dubinko, A., Matějíček, J., Rieth, Michael, Terentyev, D., Vilémová, M., Yin, C., Zhang, T., Zinovev, A.   +8 more
core   +2 more sources

Modeling Approaches for Accounting Radiation-Induced Effect in HVDC-GIS Design for Nuclear Fusion Applications [PDF]

This paper examines the modeling approaches used to analyze the electric field distribution in high-voltage direct-current gas-insulated systems (HVDC-GISs) used for the acceleration grid power supply (AGPS) of neutral beam injectors (NBIs).
Bettini P., Frescura A., Lucchini F., Marconato N., Urazaki Junior K.   +4 more
core   +1 more source