ITER-like divertor target for DEMO: Design study and fabrication test

摘要

As a major in-vessel component of a tokamak-type fusion reactor, the divertor is mainly in charge of removal of particles and partial power exhaust via scrape-off layer. The target plate of the divertor is directly exposed to non-uniform high heat flux on the surface by particle bombardment and radiation. In the case of ITER and a DEMO reactor, the peak surface heat flux is expected to reach up to 10 MW/m(2) during normal operation and 20 MW/m(2) during slow transient events like loss of plasma detachment.