Results 141 to 150 of about 2,258 (214)
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Preliminary environmental radiation considerations for CFETR

Fusion Engineering and Design, 2019
Abstract Since Chinese fusion engineering test reactor (CFETR) stepped into the engineering design phase, it was significant to discuss the environmental radiation issues considering both Chinese radiation safety regulations and lessons learned from international thermonuclear experimental reactor (ITER) being constructed in France.
Baojie Nie   +3 more
openaire   +1 more source

Research on Key Technologies of Quench Detection for CFETR TF Prototype Coil

IEEE transactions on applied superconductivity
The design and development of quench detection for the China Fusion Engineering Test Reactor (CFETR) toroidal field (TF) prototype coil is in progress, which is expected to be completed in the fourth quarter of 2025.
Teng Wang   +6 more
semanticscholar   +1 more source

The Reliability Design of CFETR Divertor

IEEE Transactions on Plasma Science, 2018
The steady state with duty cycle time 0.3–0.5 of Chinese fusion engineering testing reactor (CFETR) is a big challenge. To realize this goal, the divertor should be reliable. At the preconceptual phase of CFETR design, reliability engineering is engaged to determine how reliable of divertor is and how much level of reliability of divertor should be ...
Lei Cao   +3 more
openaire   +1 more source

Predictive Analysis of the Current Sharing Temperature Test of the CFETR CSMC

IEEE transactions on applied superconductivity
The Central Solenoid Model Coil (CSMC) has been manufactured and assembled as part of the R&D projects for the China Fusion Engineering Test Reactor (CFETR), and will be tested at ASIPP.
A. Sang   +7 more
semanticscholar   +1 more source

Engineering conceptual design of CFETR divertor

Fusion Engineering and Design, 2015
Abstract The China Fusion Engineering Test Reactor (CFETR), which is in conceptual design phase, aims at producing fusion power of 50–200 MW with tritium breeding ratio of ∼1.2 and duty cycle time of 0.3–0.5. Its designed main parameters are major/minor radii of 5.7 m/1.6 m and plasma current of 10 MA.
Xuebing Peng   +5 more
openaire   +1 more source

Formation of snowflake diverted equilibria of CFETR

Fusion Engineering and Design, 2017
Abstract The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present three snowflake (SF) divertor configurations (SF+, exact SF, SF−), to demonstrate the possibility of attaining these SF configurations with two special additional poloidal-field (PF ...
H. Li   +5 more
openaire   +1 more source

Tritium transport analysis for CFETR WCSB blanket

Fusion Engineering and Design, 2017
Abstract Water Cooled Solid Breeder (WCSB) blanket was put forward as one of the breeding blanket candidate schemes for Chinese Fusion Engineering Test Reactor (CFETR). In this study, a simplified tritium transport model was developed. Based on the conceptual engineering design, neutronics and thermal-hydraulic analyses of CFETR WCSB blanket, tritium
Pinghui Zhao   +5 more
openaire   +1 more source

Progress of engineering design of CFETR diagnostics

Fusion Engineering and Design, 2020
Abstract The primary mission of the China Fusion Engineering Test Reactor (CFETR) is to demonstrate the fusion energy production in self-sufficient burning with different-advanced operation scenarios. Due to the very harsh nuclear environment in CFETR which is much worse than that in ITER, new strategy and regulation need to be set up for reasonable ...
L.Q. Hu, Y. Liu
openaire   +1 more source

Gyrokinetic simulation of electromagnetic instabilities in CFETR steady-state scenario

Plasma Science and Technology
This study performs linear electromagnetic simulations with the gyrokinetic code NLT to examine the dominant instabilities across different radial positions in the CFETR steady-state scenario featuring internal transport barrier (ITB).
Ruzhi 汝志 TANG 唐   +5 more
semanticscholar   +1 more source

Evaluation of finite orbit width effect on alpha and NBI ions heating in CFETR scenarios

Plasma Physics and Controlled Fusion
Impact of finite orbit width (FOW) effect on fast ion heating and fusion performance in China Fusion Engineering Test Reactor (CFETR) scenarios is investigated using a test particle code particle tracer code (PTC) and integrated modeling (IM) within the ...
Luoyu Chen   +5 more
semanticscholar   +1 more source

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