ITER
node · earth
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.
Read in · 1
Evidence · 2
Timeline
No dated observations are stored for this object. Atlas shows what was observed and when — it does not infer a history.
Connections · 4
- Plasma-facing materials and first walluses
- Tritium breeding blanketparticipated_in
- Tritiumconstrained_by
- Tokamak (toroidal magnetic confinement)uses
Assembled narrative · 1
Assembled from 51 blocks · 2 evidence · 34 related
- Story
- 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.
- Knowledge
- Tokamak (toroidal magnetic confinement)
- Tritium breeding blanket
- ITER
- Tritium
- Plasma-facing materials and first wall
- Connections
- Plasma-facing materials and first wall
- Tritium breeding blanket
- Tritium
- Tokamak (toroidal magnetic confinement)
- Joint European Torus (JET)
- ITER adopts the 2016 reference baseline
- ITER presents an updated project baseline to the ITER Council
- ITER's declared target date for the start of deuterium-tritium operation
- ITER
- Breakeven
- ITER presents an updated project baseline to the ITER Council
- Lithium (as breeding feedstock)
- ITER
- Tritium
- ITER's declared target date for the start of deuterium-tritium operation
- Tokamak (toroidal magnetic confinement)
- Inertial confinement fusion
- ITER
- Tritium breeding blanket
- Private fusion sector
- JET's DTE1 campaign sets the first deuterium-tritium fusion power record
- JET's DTE2 campaign releases 59 MJ in a single pulse
- NIF achieves target gain greater than unity for the first time
- JET sets the single-pulse fusion energy record of 69.26 MJ
- JET ceases plasma operations after 105,842 pulses
- ITER's declared target date for the start of deuterium-tritium operation
- Fusion triple product (n·T·τ_E)
- Tritium
- Deuterium
- Stellarator
- ITER
- Joint European Torus (JET)
- EAST (Experimental Advanced Superconducting Tokamak)
- JET's DTE1 campaign sets the first deuterium-tritium fusion power record
- JET's DTE2 campaign releases 59 MJ in a single pulse
- JET sets the single-pulse fusion energy record of 69.26 MJ
- ITER presents an updated project baseline to the ITER Council
- EAST sustains a high-confinement plasma for 1,066 seconds
- Commonwealth Fusion Systems' declared target for net energy gain at SPARC
- Evidence
- ITER's current programme targets, the magnitude of slippage against the 2016 reference baseline, and the change of first wall material to tungsten
- 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
Observed changes · 0
No public Signals are attached to this object. Signals show what changed and when it was observed — never a direction or a rank.
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