The 17 equatorial ports provide the main access to the ITER plasma (one port is obscured by the tangential neutral beam ducts). These are therefore used for
- radio-frequency plasma heating antennae (3 ports);
- neutral beam ducts (2 ports initially, up to 3 possible);
- port limiters (2 ports);
- test blanket modules (3 ports);
- plasma diagnostics (6 dedicated ports, but also present in other port plugs)
- remote handling (4 ports, shared with port limiter, 2 shared with diagnostics)
The 9 divertor ports accommodate eight torus cryopumps, diagnostics, glow-discharge cleaning system, pellet and gas injection, and an in-vessel viewing system. Three divertor ports are also used for the remote replacement of the divertor cassettes, which are inserted radially and then slid toroidally and clamped to vessel rails.
The 9 divertor ports accommodate eight torus cryopumps, diagnostics, glow-discharge cleaning system, pellet and gas injection, and an in-vessel viewing system. Three divertor ports are also used for the remote replacement of the divertor cassettes, which are inserted radially and then slid toroidally and clamped to vessel rails. |
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The 18 upper ports are used for diagnostics, and electron cyclotron current drive to counteract certain instabilities ("neoclassical tearing modes", or NTMs). Divertor level ports are used for diagnostics, remote handling of the divertor, in-vessel viewing systems, wall conditioning systems, and torus cryopumps.
The port plugs are designed for relatively rapid replacement, using a system of transfer casks to bring them to the hot cell, where they can be repaired and refurbished.