21st IEEE/NPS Symposium on Fusion Engineering SOFE 05 2005
DOI: 10.1109/fusion.2005.252957
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Exploratory Divertor Heat Load Studies for Compact Stellarator Reactors

Abstract: Divertor heat load evaluation studies are being carried out for an example compact stellarator reactor configuration modeled after the National Compact Stellarator Experiment (NCSX). Using the field line tracing technique, an initial divertor plate geometry has been obtained, with one plate per field period, which covers 15% of the plasma surface area. A plate heat load peaking factor of 14 is acceptable with reasonable core and SOL radiation fractions in order to satisfy the engineering constraint of 10 MW/M2… Show more

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Cited by 5 publications
(1 citation statement)
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“…On the physics side, it involves adapting and using codes to better assess the location of the divertor and to estimate the cor- responding heat loads [9]. On the engineering side, the effort focused on evolving a design well suited to the compact stellarator with the capability to accommodate a heat flux of 10 MW/m 2 (as a reasonable initial goal in anticipation of the physics modeling results) and which can be integrated with the in-reactor component design [10].…”
Section: Plasma Facing Componentsmentioning
confidence: 99%
“…On the physics side, it involves adapting and using codes to better assess the location of the divertor and to estimate the cor- responding heat loads [9]. On the engineering side, the effort focused on evolving a design well suited to the compact stellarator with the capability to accommodate a heat flux of 10 MW/m 2 (as a reasonable initial goal in anticipation of the physics modeling results) and which can be integrated with the in-reactor component design [10].…”
Section: Plasma Facing Componentsmentioning
confidence: 99%