Results 161 to 170 of about 2,258 (214)
Some of the next articles are maybe not open access.

A ride-through power structure for CFETR

IEEE Transactions on Dielectrics and Electrical Insulation, 2015
The China fusion engineering test reactor (CFETR) is an ITER-like tokamak system for fusion energy development. It could output 50-200 MW fusion power in phase I for demonstrating power generation with complete structure of fusion power plant, and 1 GW output power can be expected in phase II.
Hua Li   +5 more
openaire   +1 more source

Concept design of the CFETR central solenoid

Fusion Engineering and Design, 2015
Abstract China Fusion Engineering Test Reactor (CFETR) superconducting tokamak is a national scientific research project of China with major and minor radius is 5.7 m and 1.6 m respectively. The magnetic field at the center of plasma with radius as R = 5.7 m is set to be 5.0 T.
Jinxing Zheng   +7 more
openaire   +1 more source

Manufacturing Status of CFETR Central Solenoid Model Coil

IEEE Transactions on Applied Superconductivity, 2020
A central solenoid model coil (CSMC) is to verify the large-scalar superconducting coil manufacture technology for China Fusion Engineering Test Reactor (CFETR) in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The CSMC composed of Nb3Sn and NbTi hybrid superconducting magnet can reach to 12 T maximum magnetic field.
Houxiang Han   +15 more
openaire   +1 more source

CFETR equilibrium with self-consistent pedestal structure

Fusion Engineering and Design, 2017
Abstract The Chinese Fusion Engineering Test Reactor (CFETR), which aims to fill the gaps between the International Thermonuclear Experimental Reactor (ITER) and DEMO, is in the design stages. Plasma equilibrium is an important basis for tokamak plasma research.
Kai Li   +5 more
openaire   +1 more source

Progress in CFETR Power Stations Concept Study

Journal of Fusion Energy, 2014
While EAST experiment was running in 2012, the project of the China fusion engineering test reactor (CFETR) concept design was started. This ITER-like tokamak system will be the second full superconducting tokamak in China based on EAST technology. In phase I, it has 50–200 MW heat output for demonstrating power generation.
Hua Li, Ge Li, Lu Qu, Peng Fu
openaire   +1 more source

Neutronics study on HCCB blanket for CFETR

Fusion Engineering and Design, 2017
Abstract Chinese Fusion Engineering Testing Reactor (CFETR) is aimed to obtain the technologies to fill the gaps between ITER and DEMO. The helium cooled ceramic breeder (HCCB) blanket is one of the candidates for CFETR. Ceramics Li 4 SiO 4 , beryllium and helium of 8 MPa were selected as tritium breeding material, neutron multiplier and coolant ...
Zaixin Li   +5 more
openaire   +1 more source

EAST Contributions to Closing CFETR Physics Gaps

IEEE Transactions on Plasma Science, 2016
Gaps remain in physics and engineering for China Fusion Engineering Test Reactor (CFETR) design. This report will focus on the status and the challenges in high performance long pulse/steady-state (SS) operation and the power exhausting issues. The analysis shows that for the physics goal of CFETR, 200-MW-SS operation is available in the wide windows ...
Siye Ding   +4 more
openaire   +1 more source

ICRF system on CFETR

AIP Conference Proceedings, 2023
C. M. Qin   +6 more
openaire   +1 more source

Preliminary consideration of CFETR ITER-like case diagnostic system

Review of Scientific Instruments, 2016
Chinese Fusion Engineering Test Reactor (CFETR) is a new superconducting tokamak device being designed in China, which aims at bridging the gap between ITER and DEMO, where DEMO is a tokamak demonstration fusion reactor. Two diagnostic cases, ITER-like case and towards DEMO case, have been considered for CFETR early and later operating phases ...
G. S. Li   +11 more
openaire   +2 more sources

Conceptual Design and Analysis of CFETR TF Coil

Journal of Fusion Energy, 2015
China Fusion Engineering Test Reactor (CFETR) based on the Tokamak approach with superconducting magnet technology is envisioned to provide 50–200 MW fusion power and operate with a goal of an annual duty factor of 0.3–0.5. The reactor has the equivalent scale compared with ITER.
X. F. Liu, J. X. Zheng, H. Wu, S. S. Du
openaire   +1 more source

Home - About - Disclaimer - Privacy