# Magnetic Confinement Fusion: State of the Field (October 2026)

Research dossier · v1 · updated 2026-10-30 · 4,416 words · 65 sources · 28 claims · verification: verified

Tokamaks and stellarators are the main routes to fusion power based on magnetic confinement. This dossier reviews confinement regimes, edge and disruption control, stellarator optimization, plasma-facing materials, machine-learning control and results from long-pulse, high-density and deuterium-tritium experiments through 2025, with 2026 preprints flagged. The central takeaway is that key capabilities have been shown in separate devices, while integrated burning-plasma performance remains a future goal.

## Contents

- Executive summary
- Background and core concepts
- Timeline of key milestones
- State of the art
  - Tokamak confinement, the L-H transition and advanced regimes
  - Edge control, ELMs and pellets
  - Disruptions, runaway electrons and mitigation
  - Stellarators and magnetic configuration design
  - Plasma-facing components and the fuel cycle
  - Machine learning, surrogates and control
  - Quantitative benchmarks
- Open problems and active debates
- Major programs and players
- Outlook: what to watch (near term)
- Key papers
- Glossary

## Sample findings

- Tokamaks and stellarators are the two leading magnetic-confinement concepts: tokamaks rely on a large plasma current, while stellarators use three-dimensional external coils and need no large current.
- ITER's design goal is a fusion gain of about 10, corresponding to roughly 500 MW of fusion power.

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