Title :
Power and particle exhaust in an ST-FNSF
Author :
Canik, J.M. ; Gray, T.K. ; Maingi, R. ; Menard, J.E.
Author_Institution :
Oak Ridge Nat. Lab., Oak Ridge, TN, USA
Abstract :
A spherical tokamak (ST) configuration is favorable for a Fusion Nuclear Science Facility (FNSF), due to its small size and relatively low cost. However, the compactness of the ST also exacerbates the power and particle handling problems anticipated in next-step devices, since local fluxes are higher and less space is available for optimizing plasma-facing components. Here we present an analysis of the power and particle handling requirements of a candidate ST-FNSF, based on 0-D exhaust projections as well as 2-D edge plasma modeling using the SOLPS code. These show that, for reasonable assumptions on cross-field transport, operating points can be identified that are consistent with both core plasma operation and power and particle exhaust requirements.
Keywords :
Tokamak devices; fusion reactor operation; plasma boundary layers; plasma toroidal confinement; 0-D exhaust projections; 2-D edge plasma modeling; Fusion Nuclear Science Facility; SOLPS code; ST compactness; ST configuration; ST-FNSF; core plasma operation; cross-field transport; local fluxes; next-step devices; operating points; optimizing plasma-facing components; particle exhaust requirement; particle handling problem; particle handling requirement; power exhaust requirement; power handling problem; power handling requirement; spherical tokamak configuration; Ducts; Geometry; Heating; Plasma temperature; Standards; Temperature distribution; FNSF; divertor;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635482
