2012
DOI: 10.1016/j.fusengdes.2011.10.002
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An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design

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Cited by 52 publications
(33 citation statements)
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“…Plasma major radius (R) 1.2 m Plasma minor radius (a) 0.3 m Plasma elongation (Ä) 1.7 Plasma triangularity (ı) 0.7 On-axis toroidal field Bt 7 T Plasma current (Ip) 1.7 MA Areal power density (P/S) 1 MW m −2 Safety factor (q * ) 3.0 Average density (ne) 4.0 × 10 20 m −3 Average temperature (T e ) 2.7 keV current drive has the benefit of straightforward coupling of power and localized current generation. On the other hand, the efficiency of ECCD is significantly reduced due to particle trapping at r/a > 0.5, which is generally the desired location for non-inductive current profile control in Vulcan; in [7] for T e = 4.3 keV and n e = 3.7 × 10 19 m −3 the approximate current drive efficiency at midradius is 0.4 × 10 −19 A W −1 m −2 which is below calculated LHCD efficiencies and, given the low density of that simulation, can be taken as a best case scenario for Vulcan.…”
Section: Parameter Valuementioning
confidence: 99%
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“…Plasma major radius (R) 1.2 m Plasma minor radius (a) 0.3 m Plasma elongation (Ä) 1.7 Plasma triangularity (ı) 0.7 On-axis toroidal field Bt 7 T Plasma current (Ip) 1.7 MA Areal power density (P/S) 1 MW m −2 Safety factor (q * ) 3.0 Average density (ne) 4.0 × 10 20 m −3 Average temperature (T e ) 2.7 keV current drive has the benefit of straightforward coupling of power and localized current generation. On the other hand, the efficiency of ECCD is significantly reduced due to particle trapping at r/a > 0.5, which is generally the desired location for non-inductive current profile control in Vulcan; in [7] for T e = 4.3 keV and n e = 3.7 × 10 19 m −3 the approximate current drive efficiency at midradius is 0.4 × 10 −19 A W −1 m −2 which is below calculated LHCD efficiencies and, given the low density of that simulation, can be taken as a best case scenario for Vulcan.…”
Section: Parameter Valuementioning
confidence: 99%
“…The Vulcan tokamak conceptual design [1][2][3][4] (Vulcan hereafter) is intended to allow plasma-material interaction studies in reactor-like conditions. The reactor is projected to have a divertor heat flux of ∼10 MW/m 2 and high inner wall (>800 K) temperature.…”
Section: Introductionmentioning
confidence: 99%
“…At present, the application of HTS in fusion devices mainly focuses on the design and fabrication of high temperature superconducting high current conductor [4][5][6][7][8], the design and fabrication of high temperature superconducting current lead [9,10], and the concept design and small model fabrication of HTS magnet [11,12]. It was revealed that when the TF coil system operates at the temperature range of 10 to 20 K, accordingly, the manufacturing and operating cost of the device could be reduced [13]. When the operation temperature is 20 K, the cost of the refrigeration system is about 40 % lower than that under the operating temperature 2 Science and Technology of Nuclear Installations of 4.5 K, realizing that the conduction cooling technology would be available in the Tokamak magnet system [14,15].…”
Section: Introductionmentioning
confidence: 99%
“…This is the first in a series of papers [1][2][3][4] discussing the Vulcan tokamak conceptual design for reactor-relevant plasma-material interaction (PMI) science.…”
Section: Introductionmentioning
confidence: 99%