Deutelio offers the Polomac system, a hybrid magnetic-field confinement architecture that combines toroidal and helical fields with AI‑driven real‑time diagnostics to increase plasma stability and energy gain in compact fusion reactors. The modular coil and vacuum‑vessel design can be retrofitted into existing tokamak or stellarator testbeds, enabling faster, lower‑cost development of net‑positive fusion power for laboratories, venture firms, and utility developers.
Funding
Funding not disclosed
Founders
Product
Problem
Current magnetic‑confinement fusion concepts (e.g., large tokamaks and stellarators) require massive, costly hardware and still suffer from limited plasma confinement efficiency, which delays the deployment of commercial fusion power plants needed for global decarbonization.
Solution
Deutelio’s Polomac system introduces a proprietary plasma‑confinement architecture that leverages a hybrid magnetic‑field topology to increase confinement time and energy gain while reducing reactor size. The technology integrates high‑beta plasma stability controls with real‑time diagnostic feedback, enabling more compact reactor designs that can achieve net‑positive energy output sooner. By coupling advanced computational modeling with adaptive magnetic coil configurations, Polomac improves the power‑density of fusion cores and lowers the engineering overhead associated with traditional tokamak builds. This approach shortens the development cycle for pilot and commercial fusion facilities, directly supporting the net‑zero emissions roadmap.
Target Audience
Primary customers are national fusion laboratories, private fusion venture firms, and utility‑scale energy developers seeking compact, high‑performance confinement solutions for next‑generation fusion reactors.
Features
- Hybrid magnetic‑field topology that combines toroidal and helical components for enhanced plasma stability and confinement time
- High‑beta operation regime supported by active feedback control loops using real‑time plasma diagnostics (magnetics, interferometry, Thomson scattering)
- Modular coil and vacuum vessel design that can be retrofitted into existing tokamak or stellarator testbeds, reducing capital expenditures
- AI‑driven control algorithms that optimize plasma shape, density, and temperature in situ, minimizing disruptions and maximizing fusion gain
- Integrated multi‑physics simulation suite (MHD, kinetic, neutron transport) for rapid design iteration and performance prediction
- Scalable engineering framework allowing transition from laboratory‑scale experiments to pilot‑scale power plants with minimal redesign
- Materials‑qualified for high neutron flux environments, incorporating low‑activation alloys and advanced ceramic composites for extended component life