The advanced tokamak path to a compact net electric fusion pilot plant. (19th March 2021)

• Record Type: Journal Article
• Authors: Buttery, R.J.; Park, J.M.; McClenaghan, J.T.; Weisberg, D.; Canik, J.; Ferron, J.; Garofalo, A.; Holcomb, C.T.; Leuer, J.; Snyder, P.B.
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 61:Number 4(2021)
• Publication Date: 2021-03-19
• Subjects: advanced tokamak -- pilot plant -- fusion energy -- compact; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/abe4af
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: Physics-based simulations project a compact net electric fusion pilot plant with a nuclear testing mission is possible at modest scale based on the advanced tokamak concept, and identify key parameters for its optimization. These utilize a new integrated 1.5D core-edge approach for whole device modeling to predict performance by self-consistently applying transport, pedestal and current drive models to converge fully non-inductive stationary solutions, predicting profiles and energy confinement for a given density. This physics-based approach leads to new insights and understanding of reactor optimization. In particular, the levering role of high plasma density is identified, which raises fusion performance and self-driven 'bootstrap currents', to reduce current drive demands and enable high pressure with net electricity at a compact scale. Solutions at 6–7 T, ∼4 m radius and 200 MW net electricity are identified with margins and trade-offs possible between parameters. Current drive comes from neutral beam and ultra-high harmonic (helicon) fast wave, though other advanced approaches are not ruled out. The resulting low recirculating power in a double null configuration leads to a divertor heat flux challenge that is comparable to ITER, though reactor solutions may require more dissipation. Strong H-mode access (x2 margin over L–H transition scalings) and ITER-like heat fluxes are maintained with ∼20%–60% core radiation, though effects on confinement need further analysis. Neutron wall loadings appear tolerable. The approach would benefit from high temperature superconductors, as higher fields would increase performance margins while potential for demountability may facilitate nuclear testing. However, solutions are possible with conventional superconductors. An advanced load sharing and reactive bucking approach in the device centerpost region provides improved mechanical stress handling. The prospect of an affordable test device which could close the loop on net-electric production and conduct essential nuclear materials and breeding research is compelling, motivating research to validate the techniques and models employed here.