Results 61 to 70 of about 495 (172)

Activation Calculation and Analysis for CFETR Blanket

open access: yesInternational Journal of Magnetism & Nuclear Science, 2016
With a Monte Carlo code MCNPX and an activation calculation code FISPACT-2007, nuclear heart, radioactivity and shutdown dose rate for the breeding blanket of China fusion engineering test reactor (CFETR) have been calculated. The calculation results show that the total radioactivity is 2.34x1019Bq at shutdown after one year operation and the total ...
Jiang S, Chen Z, Xu XG
openaire   +2 more sources

Conceptual design of CFETR ECRH equatorial launcher and upper launcher [PDF]

open access: yes, 2019
The Electron Cyclotron Resonance Heating (ECRH) system of China Fusion Engineering Test Reactor (CFETR) is designed to inject 20 MW RF power into the plasma for heating and current drive (H&CD) applications.
Fukun Liu   +8 more
core   +2 more sources

Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR [PDF]

open access: yes, 2019
Since the last IAEA Fusion Energy Conference in 2016, the EAST physics experiments have been developed further in support of high-performance steady-state operation for ITER and CFETR. First demonstration of a >100 s time scale long-pulse steady-state
Ding, B. J.   +76 more
core   +1 more source

Cabling technology of Nb3Sn conductor for CFETR Central Solenoid Model Coil

open access: yes, 2016
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils.
Wei, Z.   +7 more
core   +1 more source

Performance evaluation of the CFETR central solenoid model coil under operating conditions

open access: yesNuclear Fusion
The central solenoid model coil (CSMC), developed by the Institute of Plasma Physics, Chinese Academy of Sciences, is designed to meet the engineering requirements of Chinese Fusion Engineering Testing Reactor (CFETR).
Xiaohui Guan   +7 more
doaj   +1 more source

Preliminary Design of a Heat Pipe-Cooled Blanket for CFETR

open access: yes, 2021
Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are
Dianle Wang, Yun Guo
core   +1 more source

Multi-functional Dual-arm actuator system design for Tokamak divertor maintenance

open access: yesNuclear Engineering and Technology
During the remote handling maintenance of the divertor in the China Fusion Engineering Test Reactor (CFETR), a significant gap was observed between the repeatability performance of the CFETR Multipurpose Overload Robot (CMOR)—a key component—and the ...
Ruochen Yin   +4 more
doaj   +1 more source

Stability analysis on Nb3Sn sample conductor of CFETR central solenoid model coil [PDF]

open access: yes, 2018
The magnet system of China fusion engineering test reactor (CFETR) includes toroidal field, central solenoid (CS) and poloidal field coils. The design and fabrication of CS coil are most significant and challenging for China due to the lack of experience.
Shi, Yi   +17 more
core   +1 more source

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