Results 71 to 80 of about 1,196 (172)

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

open access: yesNuclear 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   +6 more
doaj   +1 more source

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

open access: yes
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  

Investigate the impact of different neutron source models on the neutronics performance for CFETR

open access: yesAIP Advances
The China Fusion Engineering Test Reactor (CFETR) is a magnetic confinement tokamak experimental device currently under development in China, which is used to bridge the scientific and technical gaps between the International Thermonuclear Experimental ...
Jie Zhang, Jie Li, Xiaogang Liu
doaj   +1 more source

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

open access: yes, 2020
Antusch, Steffen   +8 more
core   +2 more sources

An OpenFOAM multi-region solver for tritium transport modeling in fusion systems [PDF]

open access: yes
The transport, permeation and retention of tritium inside nuclear fusion reactors is a topic of great interest due to the scarcity of the isotope, its ease of diffusion through materials and its radioactivity.
Giannetti, Fabio   +2 more
core   +1 more source

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

open access: yes
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.   +4 more
core   +1 more source

Design of a mobile lifting and transportation platform for heavy component in fusion reactor [PDF]

open access: yes
This thesis introduces and designed a mobile lifting and transport platform, consisting of a background introduction, platform model design, and finite element analysis.
Cao, Guoyan
core  

Research on Operation Mode of Energy Storage System for Thermonuclear Fusion Power Plant

open access: yes南方能源建设
[Introduction] As a new form of nuclear energy utilization that is green and clean, nuclear fusion is regarded as the "ultimate energy" of mankind in the future and also as an inevitable route for China's energy development. In thermonuclear fusion power
Yan LIN   +4 more
doaj   +1 more source

Research on motion control algorithms for the blanket remote maintenance robot [PDF]

open access: yes
The China Fusion Engineering Test Reactor (CFETR) is a tokamak-type fusion reactor designed to bridge the gap between the International Thermonuclear Experimental Reactor and the demonstration fusion reactor. After the shutdown of the fusion reactor, the
Li, Dongyi
core  

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