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ITER

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ITER is a single very large tokamak under construction at Saint-Paul-lès-Durance, near Cadarache in southern France, built by a seven-member international collaboration. Its scientific goal is to produce a burning deuterium-tritium plasma at large scale, not to generate electricity: ITER has no turbine and no generator. Its schedule has slipped repeatedly. Under the updated baseline presented to the ITER Council in June 2024, the start of research operations is a stated target of 2034, full magnetic energy and plasma current in 2036, and the start of deuterium-tritium operation in 2039 — respectively three and four years later than the 2016 reference baseline, and much later than earlier plans. The updated baseline also changed the plasma-facing first wall material from beryllium to tungsten and brought forward installation of the divertor and blanket shield blocks so that the machine is more complete at first operation. All of these are programme targets and design decisions, not predictions of outcome.

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Evidence · 2
Timeline

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Connections · 4
Assembled narrative · 1

Assembled from 51 blocks · 2 evidence · 34 related

  1. Story
  2. ITER is a single very large tokamak under construction at Saint-Paul-lès-Durance, near Cadarache in southern France, built by a seven-member international collaboration. Its scientific goal is to produce a burning deuterium-tritium plasma at large scale, not to generate electricity: ITER has no turbine and no generator. Its schedule has slipped repeatedly. Under the updated baseline presented to the ITER Council in June 2024, the start of research operations is a stated target of 2034, full magnetic energy and plasma current in 2036, and the start of deuterium-tritium operation in 2039 — respectively three and four years later than the 2016 reference baseline, and much later than earlier plans. The updated baseline also changed the plasma-facing first wall material from beryllium to tungsten and brought forward installation of the divertor and blanket shield blocks so that the machine is more complete at first operation. All of these are programme targets and design decisions, not predictions of outcome.
  3. Knowledge
  4. Tokamak (toroidal magnetic confinement)
  5. Tritium breeding blanket
  6. ITER
  7. Tritium
  8. Plasma-facing materials and first wall
  9. Connections
  10. Plasma-facing materials and first wall
  11. Tritium breeding blanket
  12. Tritium
  13. Tokamak (toroidal magnetic confinement)
  14. Joint European Torus (JET)
  15. ITER adopts the 2016 reference baseline
  16. ITER presents an updated project baseline to the ITER Council
  17. ITER's declared target date for the start of deuterium-tritium operation
  18. ITER
  19. Breakeven
  20. ITER presents an updated project baseline to the ITER Council
  21. Lithium (as breeding feedstock)
  22. ITER
  23. Tritium
  24. ITER's declared target date for the start of deuterium-tritium operation
  25. Tokamak (toroidal magnetic confinement)
  26. Inertial confinement fusion
  27. ITER
  28. Tritium breeding blanket
  29. Private fusion sector
  30. JET's DTE1 campaign sets the first deuterium-tritium fusion power record
  31. JET's DTE2 campaign releases 59 MJ in a single pulse
  32. NIF achieves target gain greater than unity for the first time
  33. JET sets the single-pulse fusion energy record of 69.26 MJ
  34. JET ceases plasma operations after 105,842 pulses
  35. ITER's declared target date for the start of deuterium-tritium operation
  36. Fusion triple product (n·T·τ_E)
  37. Tritium
  38. Deuterium
  39. Stellarator
  40. ITER
  41. Joint European Torus (JET)
  42. EAST (Experimental Advanced Superconducting Tokamak)
  43. JET's DTE1 campaign sets the first deuterium-tritium fusion power record
  44. JET's DTE2 campaign releases 59 MJ in a single pulse
  45. JET sets the single-pulse fusion energy record of 69.26 MJ
  46. ITER presents an updated project baseline to the ITER Council
  47. EAST sustains a high-confinement plasma for 1,066 seconds
  48. Commonwealth Fusion Systems' declared target for net energy gain at SPARC
  49. Evidence
  50. ITER's current programme targets, the magnitude of slippage against the 2016 reference baseline, and the change of first wall material to tungsten
  51. ITER is designed to test breeding blanket mock-ups rather than to operate a closed breeding cycle, and no fusion device has yet demonstrated tritium self-sufficiency
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