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Journal: Fusion Engineering and Design

Progress in the Engineering Design and Assessment of the European DEMO First Wall and Divertor Plasma Facing Components

Reduced beryllium requirements and increased tritium production in mixed bed breeder blankets

Definition of the basic DEMO tokamak geometry based on systems code studies

Spatially and temporally varying tritium generation in solid-typebreeder blankets

Optimal design of a toroidal field magnet system and cost of electricity implications for a tokamak using high temperature superconductors

Reducing beryllium content in mixed bed solid-type breeder blankets

A new Disruption Mitigation System for Deuterium – Tritium Operation at JET

Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor

Implications of Toroidal Field Coil Stress Limits on Power Plant Design Using PROCESS

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