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      Projections of H-mode access and edge pedestal in the SPARC tokamak

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          Abstract

          In order to inform core performance projections and divertor design, the baseline SPARC tokamak plasma discharge is evaluated for its expected H-mode access, pedestal pressure and edge-localized mode (ELM) characteristics. A clear window for H-mode access is predicted for full field DT plasmas, with the available 25 MW of design auxiliary power. Additional alpha heating is likely needed for H-mode sustainment. Pressure pedestal predictions in the developed H-mode are surveyed using the EPED model. The projected SPARC pedestal would be limited dominantly by peeling modes and may achieve pressures in excess of 0.3 MPa at a density of approximately 3 × 10 20 m −3. High pedestal pressure is partially enabled by strong equilibrium shaping, which has been increased as part of recent design iterations. Edge-localized modes (ELMs) with >1 MJ of energy are projected, and approaches for reducing the ELM size, and thus the peak energy fluence to divertor surfaces, are under consideration. The high pedestal predicted for SPARC provides ample margin to satisfy its high fusion gain ( Q) mission, so that even if ELM mitigation techniques result in a 2× reduction of the pedestal pressure, Q > 2 is still predicted.

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          H mode power threshold database for ITER

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            Overview of the SPARC tokamak

            The SPARC tokamak is a critical next step towards commercial fusion energy. SPARC is designed as a high-field ( \(B_0 = 12.2\) T), compact ( \(R_0 = 1.85\) m, \(a = 0.57\) m), superconducting, D-T tokamak with the goal of producing fusion gain \(Q>2\) from a magnetically confined fusion plasma for the first time. Currently under design, SPARC will continue the high-field path of the Alcator series of tokamaks, utilizing new magnets based on rare earth barium copper oxide high-temperature superconductors to achieve high performance in a compact device. The goal of \(Q>2\) is achievable with conservative physics assumptions ( \(H_{98,y2} = 0.7\) ) and, with the nominal assumption of \(H_{98,y2} = 1\) , SPARC is projected to attain \(Q \approx 11\) and \(P_{\textrm {fusion}} \approx 140\) MW. SPARC will therefore constitute a unique platform for burning plasma physics research with high density ( \(\langle n_{e} \rangle \approx 3 \times 10^{20}\ \textrm {m}^{-3}\) ), high temperature ( \(\langle T_e \rangle \approx 7\) keV) and high power density ( \(P_{\textrm {fusion}}/V_{\textrm {plasma}} \approx 7\ \textrm {MW}\,\textrm {m}^{-3}\) ) relevant to fusion power plants. SPARC's place in the path to commercial fusion energy, its parameters and the current status of SPARC design work are presented. This work also describes the basis for global performance projections and summarizes some of the physics analysis that is presented in greater detail in the companion articles of this collection.
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              Divertor heat flux challenge and mitigation in SPARC

              Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m −2 . This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (~11–34 MJ m −2 ) are comparable with those for ITER. However, the relatively short pulse length (~25 s pulse, with a ~10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ~1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.
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                Author and article information

                Contributors
                Journal
                Journal of Plasma Physics
                J. Plasma Phys.
                Cambridge University Press (CUP)
                0022-3778
                1469-7807
                October 2020
                September 29 2020
                October 2020
                : 86
                : 5
                Article
                10.1017/S0022377820001300
                3a4ac9d4-08b9-424c-8390-451e06bb29f6
                © 2020

                http://creativecommons.org/licenses/by-nc-nd/4.0/

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