Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor

The latest progress in the design of water-cooled lithium–lead (WCLL) tritium extraction and removal (TER) system for European DEMO tokamak reactor is presented. implementation optimization conceptual TER are performed order to manage concentration LiPb ancillary systems, control chemistry, remove accumulated corrosion activated products (in particular, helium generated BB), store LiPb, empty BB segments, shield equipment due activation, accommodate possible overpressure LiPb. volumes inboard (IB) outboard (OB) modules separately managed different pressure drops required mass flow rates plasma operational phases. Therefore, by 6 loops: 4 loops OB segments 2 IB segments. Each one a closed loop with forced circulation liquid metal through other systems. presents new CAD drawings integration TEU into building, designed on basis an experimental characterization carried out permeator against vacuum (PAV) gas–liquid contactor (GLC) technologies, two most promising technologies from metal.