Nuclear Fusion · 2009 · 163 citations · 21 references
EngineeringDesignNuclear EngineeringFusion EngineeringHeat TransferPlasma PhysicsFusion Reactor MaterialsMagnetic Confinement FusionNuclear FusionPlasma ConfinementReactor Core DesignReactor DesignBlanket ArrangementBlanket DesignBlanket MaterialsBlanket Module DesignCompact Reactor DesignDivertor Power HandlingSolid Breeder MaterialsVertical Stability
The study designs a compact low‑aspect‑ratio DEMO reactor, SlimCS, with a torus configuration featuring a water‑cooled solid breeder blanket, segmented replaceable and permanent blankets, and a sector‑wide conducting shell for vertical stability and high‑beta access. Design progress shows SlimCS can achieve fuel self‑sufficiency with an ideally fabricated blanket, but the divertor plate must handle ≤8 MW m⁻², a critical constraint for DEMO’s power handling.
The design progress in a compact low aspect ratio (low A ) DEMO reactor, ‘SlimCS’, and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m −2 or lower, which can be a critical constraint for determining a handling power of DEMO.
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Design study of fusion DEMO plant at JAERI
K. Tobita, Shuichi Nishio, Mikio Enoeda et al. · Fusion Engineering and Design · 2005 · 145 citations
Disruptions and disruption mitigation
V. Riccardo, Jet Contributors · Plasma Physics and Controlled Fusion · 2003 · 100 citations