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Research dossier · version 1 · updated Oct 30, 2026

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

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.

4,416 words65 sources28 evidence-mapped claims12 benchmarks15 timeline events✓ citation-verified Oct 30, 2026

AI-assisted synthesis of the cited literature, independently fact-checked against its sources; not peer reviewed.

Contents

  1. Executive summary
  2. Background and core concepts
  3. Timeline of key milestones
  4. State of the art
  5. Tokamak confinement, the L-H transition and advanced regimes
  6. Edge control, ELMs and pellets
  7. Disruptions, runaway electrons and mitigation
  8. Stellarators and magnetic configuration design
  9. Plasma-facing components and the fuel cycle
  10. Machine learning, surrogates and control
  11. Quantitative benchmarks
  12. Open problems and active debates
  13. Major programs and players
  14. Outlook: what to watch (near term)
  15. Key papers
  16. 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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