2006
DOI: 10.1016/j.fusengdes.2005.09.074
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Concept of core and divertor plasma for fusion DEMO plant at JAERI

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Cited by 13 publications
(15 citation statements)
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“…Physics parameters of the core plasma such as temperature, density, collisionality, normalized Larmor radius, ratio of the required normalized beta to the ideal normalized beta and the required confinement enhancement factor HH are very similar between ITER and DEMO [13] as shown in Table 2. The most distinctive feature of a DEMO fusion reactor is a much higher heating power (alpha pulse additional heating), typically 500 MW or higher.…”
Section: Plasma Surface Interaction Issues In a Next Fusion Reactormentioning
confidence: 91%
“…Physics parameters of the core plasma such as temperature, density, collisionality, normalized Larmor radius, ratio of the required normalized beta to the ideal normalized beta and the required confinement enhancement factor HH are very similar between ITER and DEMO [13] as shown in Table 2. The most distinctive feature of a DEMO fusion reactor is a much higher heating power (alpha pulse additional heating), typically 500 MW or higher.…”
Section: Plasma Surface Interaction Issues In a Next Fusion Reactormentioning
confidence: 91%
“…Using CORSICA, we have found SXD equilibria for many devices where SXD could be crucial including ͑a͒ tokamaks with copper coils: aspect ratios A = 1.4 for a component test facility ͑CTF͒, 13 A = 1.4 for the Mega Amp Spherical Tokamak ͑MAST͒, 17 A = 1.8 for the National Spherical Tokamak Experiment ͑NSTX͒, 18 the National High-Power Tokamak Experiment ͑NHTX͒, 14 one variant of A = 2.0 CFNS, 6 the A = 3.5 Fusion Development Facility ͑FDF͒ ͑Ref. 15͒ and ͑b͒ tokamaks with superconducting coils all outside the TF coils: A = 2.6 for the SLIMCS reactor 11 and A = 4 for ARIES-AT. 10 Various gains due to SXD are summarized in Table I and two examples are shown in Fig.…”
Section: The Super-x Divertormentioning
confidence: 99%
“…Neutral beam injection (NBI) and waves in electron cyclotron range of frequencies (ECRF) are considered to be external current drive tools. A system code analysis indicates that the required CD power in the ramp-up phase is about 20 MW higher than that in the steady-state operation (60 MW) [11].…”
Section: Main Option "Slim Cs"mentioning
confidence: 94%
“…The parameters of each options are chosen by a systems code analysis. In the parameter selection, the plasma elongation (κ) is determined to keep vertical stability of plasma and the normalized beta (β N ) is assumed to have A-and κ-dependence as formulated by Lin-Liu and Stambaugh [10]; the design values of κ and β N are set to 75% and lower than 78% of the limits given by the formula, respectively [11].…”
Section: Search For Compact Reactor Conceptmentioning
confidence: 99%
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