2005
DOI: 10.1016/j.jnucmat.2004.10.072
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Long-pulse discharges by synergy of LHW and IBW heating in the HT-7 tokamak

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Cited by 18 publications
(18 citation statements)
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“…The Hefei Tokamak-7 (HT-7) is a superconducting tokamak [7][8][21][22][23][24][25][26], and it was reconstructed from the original Russian T-7 tokamak in 1994. It has a major radius of R = 1.22 m, minor radius of a = 0.27 m in the circular cross section.…”
Section: Methodsmentioning
confidence: 99%
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“…The Hefei Tokamak-7 (HT-7) is a superconducting tokamak [7][8][21][22][23][24][25][26], and it was reconstructed from the original Russian T-7 tokamak in 1994. It has a major radius of R = 1.22 m, minor radius of a = 0.27 m in the circular cross section.…”
Section: Methodsmentioning
confidence: 99%
“…The new GBST1308 doped graphite was used as limiter material. All carbon titles were coated with 100 µm Silicon Carbide (SiC) functional gradient coating [21]. The two poloidal water-cooling limiters and one toroidal water-cooling belt limiter at high field side were developed in 2002 [21].…”
Section: Methodsmentioning
confidence: 99%
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