Speaker
Description
Oral presentation (20 min) + Q&A (10 min)
The 19 Toroidal Field (TF) coils, including one spare, have been manufactured by Japan and Europe and have been delivered on ITER site. The Poloidal Field Coil PF1, procured by Russia has also arrived on site. The new baseline schedule has given the Project the opportunity to build a magnet test bench (MCTB) on site in order to test some of the ITER TF coils and the PF1 coil taking into account the new assembly schedule. The most complete magnet integrated tests will be performed to gain experience for the tokamak commissioning.
The main objective of the tests is to check the overall magnet performance (joint resistance, mechanical deformation, operating conditions) and confirm the proper operation of the coils. One major risk mitigation is the check of the ground insulation and ground protection. The TF coils will be energized at half nominal current (34 kA) to optimize the testing plan and meet the tokamak assembly schedule. Only the TFC19 spare coil and PF1 will be tested at nominal current, respectively 68 kA and 48 kA. The coils will be cooled with supercritical helium at 4.75 K and 0.46 MPa provided by the ITER cryoplant.
Most of the components of the test facility will be ITER relevant and will allow the test of the instrumentation chains and control logics foreseen for the ITER operation. An ITER Cold Terminal Box will be connected to the coil for the helium and electrical supplies. The cryogenic system will provide enough refrigeration capacity with one out of the three ITER refrigeration cold boxes and will supply supercritical helium to the TF winding pack, casing and busbars. One important system to be tested will be the magnet protection system to demonstrate the quench detection capabilities (primary, secondary and safety class detection).
A 21 m long- 11 m large and 6 m height cryostat is being manufactured to position horizontally either a TF coil or PF1 coil. A dedicated power supply will energize the coil and a Fast Discharge Unit will protect the coil in case of Fast discharge and quench.
The presentation gives an overview of the design of the test facility, the progress status of the main components and the testing program.
"The views and opinions expressed herein do not necessarily reflect those of the ITER Organization”
