Gyrokinetic Simulations for Spherical Tokamak Divertor Design
Nuclear fusion is an attractive source of energy because the fuel is abundant and it produces low levels of carbon emissions. The tokamak, which confines a plasma using magnetic fields, is the most mature nuclear fusion reactor concept. Maximizing energy confinement by minimizing turbulent heat loss while also minimizing damage to the reactor is essential for producing efficient, commercially viable fusion reactors. Heat exhaust methods used in the scrape-off layer (SOL) of the tokamak greatly influence performance. Conventional heat exhaust methods focus on minimizing reactor damage rather than maximizing confinement. The low-recycling regime, a newer approach, focuses on maximizing energy confinement. Studying the low-recycling regime, which features a high temperature and low density SOL, requires new modeling tools. We have developed the gyrokinetic code Gkeyll into an appropriate tool, and we use it to demonstrate the viability of the low-recycling regime with simulations of the Spherical Tokamak for Energy Production (STEP). Our work addresses several key issues with low recycling. Our simulation results indicate that a high SOL temperature and low SOL density could be achieved without using a lithium divertor plate. This is an important step because lithium divertor plates evaporate when exposed to large heat fluxes, which lowers the SOL temperature, counteracting the desired regime. Our simulation results also indicate that kinetic effects can lower the peak heat flux on the divertor plate, which would improve reactor survivability, and confine sputtered impurities to the divertor region, which would prevent core contamination and performance degradation.