Speaker
Yuhu Zhai
(Engineering)
Description
ITER is the world’s largest fusion device currently under construction in the South of France with over 60 diagnostic systems to be installed inside the port plugs, the interspace or the port cell region of various diagnostic ports. The plasma facing Diagnostic First Wall (DFW) and its supporting Diagnostic Shielding Modules (DSM) are designed to protect front-end diagnostics from plasma neutron and radiation while providing apertures for diagnostic access to the plasma. The design of ITER port plug structures (PPS) including the DFWs and DSMs is largely driven by the electromagnetic loads induced on these passive structural components during plasma disruptions and vertical displacement events (VDEs). Unlike the DFW and DSM, the design of ITER diagnostic system, however, is likely driven by the steady-state thermal loads from plasma volumetric and surface heating; and the dynamic response of in-port components attached to the port-specific DSM or PPS as a result of transient electromagnetic loads induced on the Vacuum Vessel (VV) and the port extension during asymmetric plasma VDEs. We investigate in this study the worst plasma disruption load scenarios for diagnostic systems of varying size and location, and summarize the steady-state thermal, transient electromagnetic and VV VDE inertial loads for equatorial port and upper port diagnostic systems such as toroidal interferometer and polarimeter (TIP), electron cyclotron emission (ECE) in E9 and wide angle viewing (WAV) system in U14 as a result of VV movements during asymmetric VDEs. We also introduce the common approach and design requirement for tenant interface load transfer for in-port diagnostic systems attached to the DSMs as one of the design engineering and integration tasks of the ITER diagnostic ports.
Co-author
Yuhu Zhai
(Engineering, Princeton Plasma Physics Laboratory, Princeton, United States)
