Project Helios
Advanced Magnetic Confinement Fusion Research & Commercialization
Architecture & Engineering
Project Helios utilizes a hybrid spherical tokamak-stellarator configuration, enabling superior plasma stability, reduced ripple losses, and continuous steady-state operation.
Superconducting Magnetics
High-temperature REBCO tapes enabling compact, high-field coils with active thermal management and quench protection systems.
Plasma Diagnostics
Multi-modal diagnostic suite including Thomson scattering, bolometry, and AI-driven edge-localized mode prediction.
AI Control Systems
Real-time reinforcement learning agents optimizing plasma shape, density, and current profile at 100kHz control loops.
Divertor Materials
Liquid lithium-metal eutectic divertor plates designed to handle 20MW/m² heat flux while breeding tritium in-situ.
Milestones & Timeline
Foundation & Core Design
Finalized hybrid tokamak-stellarator geometry. Secured $2.4B internal funding from Aevum Energy Division.
Magnet Assembly & Cryo Testing
Completed first full superconducting coil stack. Achieved 20K operational temperature with zero quench events.
First Plasma & Diagnostic Calibration
NET-100 prototype operational. Sustained deuterium plasma at 120MK for 120 seconds. AI control loops engaged.
Deuterium-Tritium Campaign
Introduction of DT fuel mix. Target Q > 2.0. Full-scale divertor stress testing under fusion neutron flux.
Grid-Connected Pilot Plant
Commercial demonstration unit online. Target continuous operation > 30 days. Regulatory certification complete.