Preprint Article Version 1 Preserved in Portico This version is not peer-reviewed

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Version 1 : Received: 17 March 2023 / Approved: 20 March 2023 / Online: 20 March 2023 (01:08:40 CET)

A peer-reviewed article of this Preprint also exists.

Sosa, D.; Palermo, I. Neutronic Assessments Towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket. Energies 2023, 16, 4430. Sosa, D.; Palermo, I. Neutronic Assessments Towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket. Energies 2023, 16, 4430.

Abstract

The Stellarator Power Plant Studies Prospective R&D Work Package among the Eurofusion Programme was settled to bring the stellarator engineering to maturity, so that stellarators and particularly the HELIAS (HELical-axis Advanced Stellarator) configuration could be a possible alternative to tokamaks. However, its complex geometry makes designing a Breeding Blanket (BB) that fully satisfies the requirements for such an HELIAS configuration a difficult task. Taking advantage of the acquired experience in BB design for DEMO tokamak, CIEMAT is leading the development of a Dual Coolant Lithium Lead (DCLL) BB for a HELIAS configuration. To answer the specific HELIAS challenges new and advanced solutions have been proposed, as the use of fully detached First Wall (FW) based on liquid metal Capillary Porous Systems (CPS). These proposed solutions have been studied in a simplified 1D model that can help to estimate the relative variations in Tritium Breeding Ratio (TBR) and displacement per atom (dpa) to verify their effectiveness to simplify the BB integration, improve the machine availability while keeping the main BB nuclear functions (i.e. tritium breeding, heat extraction and shielding). This preliminary study demonstrates that the use of FW CPS would reduce the radiation damage received by the blanket without compromising its tritium breeding performance.

Keywords

Fusion; DCLL; Breeding Blanket; HELIAS; TBR; neutronic

Subject

Computer Science and Mathematics, Mathematical and Computational Biology

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