Plasma Wall Interactions: Fusion

This lecture covers the requirements for the first wall of a fusion reactor, including withstanding high heat fluxes, keeping the plasma pure, and minimizing Tritium retention. It also discusses limiter and divertor configurations, the scrape off layer, advantages of the divertor concept, and innovative divertor configurations. Further challenges for divertors such as transients, disruptions, and plasma flow are explored. The choice of first wall materials for ITER, like tungsten and beryllium, is detailed. Various divertor configurations for DEMO and reactors are presented, emphasizing the importance of integrating plasma, atomic, and materials physics.