Plasma diagnostics fall into three categories:
- those necessary for machine protection or basic control,
- those needed for advanced performance control,
- those desirable for physics studies,
About 45 different diagnostic systems in seven main groups will be deployed around the ITER tokamak.
These diagnostics have been carefully selected to take account of their feasibility and endurance and compatibility with the nuclear environment of ITER, to minimise their impact on machine integrity and reliability, and to minimise cost.
The type of diagnostics deployed to measure the various plasma parameters needed for basic control are listed below.
Measurements and Plasma Diagnostics for Machine Protection/Basic Control |
|
| Parameters Measured | Diagnostic Group |
Shape/Position, Vertical Speed, Locked Modes A (Magnetic) |
A (Magnetic) |
| Fusion Power | B (Neutron) |
| Line-averaged Density | C (Optical/Infra-red) |
| Radiated Power from Core, X-point and Divertor Impurity & D,T Influx (main plasma & divertor) Zeff (line-averaged) |
D (Bolometric) |
| H/L-mode Indicator | E (Spectroscopic/Neutral Particle) |
| nT/nD in Core | E & F |
| ELMs (type) Runaway Electrons Divertor Plates &First Wall Surface Temperature |
F (Microwave) |
| Divertor and Duct Gas Pressure and Composition | G (Plasma-Facing Component and Operational) |
For all these diagnostics more than 220 professional years of effort in design, procurement monitoring and implementation during construction is envisaged in participating laboratories, outside the integration effort within the ITER project itself. Further such effort will be needed during the operation phase.
Further details on the overview of plasma diagnostics can be found in the ITER Technical Basis. 