Plasma Science and Technology · 2024 · 24 citations · 56 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringPlasma PhysicsThermal AnalysisFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionNeutral Beam InjectionNuclear FusionPlasma HeatingElectron Cyclotron Resonance HeatingHeating System DesignLocalized Current DriveNeutral Beam Injection HeatingPlasma Heating SystemsTokamak DesignTokamak PhysicsTokamak Plasmas
Abstract ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p- 11 B fusion, establish spherical torus/tokamak experimental scaling laws at 10’s keV ion temperature, and provide a design basis for subsequent experiments to test and realize the p- 11 B fusion burning plasma. Based on 0-dimensional (0-D) system design and 1.5-dimensional transport modelling analyses, the main target parameters of EHL-2 have been basically determined, including the plasma major radius, R 0 , of 1.05 m, the aspect ratio, A , of 1.85, the maximum central toroidal magnetic field strength, B 0 , of 3 T, and the plasma toroidal current, I p , of 3 MA. The main heating system will be the neutral beam injection at a total power of 17 MW. In addition, 6 MW of electron cyclotron resonance heating will serve as the main means of local current drive and MHD instabilities control. The physics design of EHL-2 is focused on addressing three main operating scenarios, i.e., (1) high ion temperature scenario, (2) high-performance steady-state scenario and (3) high triple product scenario. Each scenario will integrate solutions to different important issues, including equilibrium configuration, heating and current drive, confinement and transport, MHD instability, p- 11 B fusion reaction, plasma-wall interactions, etc. Beyond that, there are several unique and significant challenges to address, including establish a plasma with extremely high core ion temperature ( T i,0 > 30 keV), and ensure a large ion-to-electron temperature ratio ( T i,0 / T e,0 > 2), and a boron concentration of 10%‒15% at the plasma core; realize the start-up by non-inductive current drive and the rise of MA-level plasma toroidal current. This is because the volt-seconds that the central solenoid of the ST can provide are very limited; achieve divertor heat and particle fluxes control including complete detachment under high P / R (> 20 MW/m) at relatively low electron densities. This overview will introduce the advanced progress in the physics design of EHL-2.
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Overview of the present progress and activities on the CFETR
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A gyro-Landau-fluid transport model
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Y.K.M. Peng, D.J. Strickler · Nuclear Fusion · 1986 · 435 citations