Assessment of the He-cooled Test Divertor Module for ITER

Abstract Within the EU power plant conceptual study (PPCS), a modular He-cooled divertor concept is being investigated at the Forschungszentrum Karlsruhe to achieve a heat flux of at least 10 MW/m 2 . The intermediate-term goal of divertor development is the completion of a test divertor module (TDM) which is envisaged to be tested in ITER from 2020 onward before it will be used in DEMO. As a preparatory step, the possibility of performing such an experiment with a helium-cooled TDM in ITER is assessed. The investigation covers, e.g. checking whether the space available is sufficient and the experiment is compatible with ITER operation and RH (remote handling) procedures as well as assessing the thermohydraulic and piping layout for helium cooling.