Flat-top plasma operational space of the STEP power plant

• DOI: 10.1088/1741-4326/ad6ea2
• Publication Date: 2024-08-13T22:51:30Z
• Authors: E. Tholerus; F.J. Casson; S.P. Marsden; T. Wilson; D. Brunetti; P. Fox; S.J. Freethy; T.C. Hender; S.S. Henderson; A. Hudoba; K.K. Kirov; F. Koechl; H. Meyer; S.I. Muldrew; C. Olde; B.S. Patel; C.M. Roach; S. Saarelma; G. Xia
• Keywords: flat-top; JINTRAC; FOS: Physical sciences; QC770-798; STEP; 01 natural sciences; Physics - Plasma Physics; Plasma Physics (physics.plasm-ph); Nuclear and particle physics. Atomic energy. Radioactivity; integrated modelling; 0103 physical sciences; spherical tokamak

Abstract STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, including integrated core plasma modelling, MHD stability analysis, SOL and pedestal modelling, coil set and free boundary equilibrium solvers, and whole plant design, has been developed to specify the design parameters and to develop viable scenarios. The integrated core plasma model JETTO is used to develop individual flat-top operating points that satisfy imposed criteria for fusion power performance within operational constraints. Key plasma parameters such as normalised beta, Greenwald density fraction, auxiliary power and radiated power have been scanned to scope the operational space and to derive a collection of candidate non-inductive flat-top points. The assumed auxiliary heating and current drive is either from electron cyclotron (EC) systems only or a combination of EC and electron Bernstein waves. At present stages of transport modelling, there is a large uncertainty in overall confinement for relevant parameter regimes. For each of the two auxiliary heating and current drive systems scenarios, two candidate flat-top points have been developed based on different confinement assumptions, totalling to four operating points. A lower confinement assumption generally suggests operating points in high-density, high auxiliary power regimes, whereas higher confinement would allow access to a broader parameter regime in density and power while maintaining target fusion power performance.