Search Results - "Yao, D.M."
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The first in-vessel cryopump for EAST divertor experiment
Published in Fusion engineering and design (01-12-2010)“…To operate divertor experiment, an in-vessel cryopump was installed on the EAST tokamak in 2008. It can limit gas impurity recycling from divertor region into…”
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Journal Article Conference Proceeding -
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Development and application of limiter Langmuir probe array in EAST
Published in Fusion engineering and design (01-07-2022)“…•A newly limiter langmuir probe (LLP) array has been developed in EAST.•The LLP array has been operated in EAST since 2021.•The commissioning of EAST LLP was…”
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Formation of snowflake diverted equilibria of CFETR
Published in Fusion engineering and design (01-10-2017)“…The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present…”
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Evaluation of target-plate heat flux for a possible snowflake divertor in CFETR using SOLPS
Published in Journal of nuclear materials (01-08-2015)“…China Fusion Engineering Test Reactor (CFETR) is proposed as a good complement to ITER for demonstration of fusion energy. CFETR is based on both physics and…”
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Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak
Published in Fusion engineering and design (01-09-2019)“…An upgrade to the lower divertor is currently being planned for EAST superconducting tokamak, aiming at reaching over 400 s long-pulse H-mode operations with a…”
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High creep resistance behavior of the cast Al–Cu alloy modified by nano-scale Pr x O y
Published in Materials science & engineering. A, Structural materials : properties, microstructure and processing (2009)“…Creep behavior of the unmodified and modified cast Al–Cu alloys was investigated at temperatures from 393 to 483 K in the tension test. The creep resistance…”
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The structure analysis of ITER cryostat based on the finite element method
Published in Fusion engineering and design (01-01-2013)“…In the ITER project the cryostat is one of the most important components. Cryostat shall transfer all the loads that derive from the TOKAMAK inner basic…”
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Plasma facing components of EAST
Published in Fusion engineering and design (01-12-2010)“…EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and…”
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Journal Article Conference Proceeding -
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EAST in-vessel components design
Published in Fusion engineering and design (01-11-2005)“…Divertor and other in-vessel components are very important parts of EAST superconducting Tokamak. The primary purpose of these components is to protect the…”
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Journal Article Conference Proceeding -
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Thermal and mechanical analysis of the EAST plasma facing components
Published in Fusion engineering and design (01-11-2005)“…The Experimental Advanced Superconducting Tokamak (EAST) is an advanced steady-state plasma physics experimental device, which has a long pulse (60–1000 s)…”
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HT-7U vacuum vessel
Published in Fusion engineering and design (01-09-2003)“…The HT-7U superconducting tokamak is under construction. It is expected to complete the fabrication and installation in the next 2–3 years. Overall…”
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Test results and analyses of conductor short samples for HT-7U
Published in Cryogenics (Guildford) (01-03-2003)“…The experiments of Cable-in conduit conductor (CICC) short samples with high proportion of segregated copper strands have been carried out in SULTAN facility…”
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Journal Article Conference Proceeding -
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Design and structure analysis of the HT-7U vacuum vessel
Published in Fusion engineering and design (01-11-2001)“…The vacuum vessel of the HT-7U superconducting tokamak has a full welded structure with double wall which will be filled with borated water is used for neutron…”
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Journal Article Conference Proceeding -
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The R&D progress of the EAST (HT-7U) superconducting tokamak
Published in 20th IEEE/NPSS Symposium onFusion Engineering, 2003 (2003)“…The superconducting tokamak project HT-7U, aiming at steady-state advanced operation mode, will make a contribution to future steady-state tokamak reactors…”
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Conference Proceeding -
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Design of the HT-7U tokamak device
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)“…The HT-7U superconducting tokamak is an advanced steady-state plasma physics experimental device to be built at the Institute of Plasma Physics, the Chinese…”
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Conference Proceeding