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I. Palermo

Publications and source records attributed to I. Palermo.

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Initial evaluation of miniature ultra-high-field commercial stellarator reactors with breeding external to resistive coils

The working parameters and challenges of ultra-high-field pulsed commercial stellarator reactors of small plasma volume with breeding external to resistive coils ($transposed$ stellarator) are studied. They may allow production of commercial heat and electricity in a tiny and simple device, and contribute to the knowledge on burning plasmas. The concept is based on the previous works (V. Queral et al.) performed for the high-field experimental fusion reactor i-ASTER (J. Fus. Energy 37 2018) and the recent Distributed Divertor concept (non-resonant divertor on the full toroid; J. Fus. Energy 44 2025). The present proposal is driven by the limitation on the minimum size of typical commercial stellarator reactors (~ space for internal breeding/shielding of SC coils). This limit is about 400 $\text{m}^3$ plasma volume, as deduced from e.g. ARIES-CS, ASTER-CP-(IEEE Trans. Plasma Sci. 52 2024) and Stellaris reactors. This fact, together with the accuracy and complexity of the systems, hinders quick iterations for the fast development of stellarator reactors. The concept is based on a pulsed high-beta large-aspect-ratio stellarator of small plasma volume (2-4 $\text{m}^3$) and ultra-high magnetic field (~ 10-20 T), composed by an external monolithic coil support and internal resistive coils (alike i-ASTER and UST_3 stellarators) of high neutron transparency, thermally-adiabatic conductors, a low-recycling Distributed Divertor to extract the heat power from ionized particles (pulse length ~ 5 $τ$E), low pulsed duty cycle of 1-5%, and liquid breeding material around and externally to the reactor core. Different cases and operating points are studied. The main elements, e.g. heat power on the Distributed Divertor, radiation lifetime, and the prospect of net electricity production are evaluated. The involved challenges, impacting the potential feasibility of the concept, are assessed.

physics.plasm-ph

Physics design point of high-field stellarator reactors

The ongoing development of electromagnets based on High Temperature Superconductors has led to the conceptual exploration of high-magnetic-field fusion reactors of the tokamak type, operating at on-axis fields above 10 T. In this work we explore the consequences of the potential future availability of high-field three-dimensional electromagnets on the physics design point of a stellarator reactor. We find that, when an increase in the magnetic field strength $B$ is used to maximally reduce the device linear size $R\sim B^{-4/3}$ (with otherwise fixed magnetic geometry), the physics design point is largely independent of the chosen field strength/device size. A similar degree of optimization is to be imposed on the magnetohydrodynamic, transport and fast ion confinement properties of the magnetic configuration of that family of reactor design points. Additionally, we show that the family shares an invariant operation map of fusion power output as a function of the auxiliary power and relative density variation. The effects of magnetic field over-engineering and the $R(B)$ scaling of design points with constant neutron wall loading are also inspected. In this study we use geometric parameters characteristic of the helias reactor, but most results apply to other stellarator configurations

physics.plasm-ph