ORIGO/FUSIONOptimisation of Reactor Integration,
Geometry and Operation
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Geometry is
a starting point.

We aim to discover reactor geometries by optimising magnetic configuration, plasma physics and heating together, then carry validated designs toward physical construction.

Question the inherited geometry.

Our approach starts with the freedom to explore geometry alongside confinement, heating and engineering constraints. Accelerated, integrated modelling would help us evaluate these choices together.

The eventual ORIGO Fusion reactor may use a different geometry from the tokamak illustrated here. No final configuration has been selected; a design would require numerical verification, expert review and physical validation before construction.

Illustrative sectionInspect the plasma, coils and structure with the layer controls. This is an explanatory drawing, not a validated reactor design.
OF—FIG / 001Conceptual section
Conceptual magnetic confinement sectionA code-drawn section showing nested analytic plasma contours, surrounding vessel and structure, central column, and indicative coil positions. These are explanatory geometric shapes, not a magnetic equilibrium, engineering design or selected ORIGO Fusion architecture. Not to scale.BACCRadial direction →Vertical direction
A Plasma contoursB Coil positionsC Structure
Not to scaleExplanatory geometry — not validated

No subsystem gets designed in isolation.

Every engineering choice shifts boundary conditions elsewhere. Evaluating the couplings matters as much as optimizing each component.

01 / CONFINEMENT

Plasma & magnetic topology

Equilibrium, stability, transport, heating and particle exhaust.

02 / SYSTEMS

Materials & fuel cycle

Structural loads, neutron exposure, blanket systems, shielding and fuel handling.

03 / PLANT

Reliability & operation

Remote maintenance, uptime, net electricity, safety and maintainable construction.

Heat and particle exhaust.

Geometry optimisation must also consider how heat and particles leave the confined plasma. Exhaust links plasma performance to erosion, component life and maintenance access.

Scrape-off layer (SOL)
In a diverted tokamak, this outer plasma region carries heat and particles along open magnetic field lines toward divertor targets.
Divertor
Targets receive the plasma exhaust. Cooling and pumping systems manage the heat and remove particles, including helium ash.

Our research considers exhaust alongside geometry, materials and maintainability. The eventual exhaust configuration remains open.

Physics references: Max Planck IPP — SOL · ITER — divertor

Diverted tokamakPoloidal section
Scrape-off layer and divertor targetsIllustrative cross-section of a diverted tokamak. A marks the confined plasma inside closed contours. B marks open field-line paths in the surrounding scrape-off layer, leading toward the two divertor targets marked C below the plasma. The plasma boundary has a lower X-point. The curves illustrate topology, not a calculated magnetic equilibrium.ABC
A Confined plasmaB Scrape-off layerC Divertor targets
Illustrative diverted tokamak. Not to scale.

Make room for maintenance.

Our long-term vision includes robotic arms for inspection, repair and replacement of worn plasma-facing components and blanket modules. Designing access for these systems is part of designing the plant.

Autonomous operation and robotic maintenance remain long-term research aims, requiring physical validation and human oversight.

Integrated modelling