Design of a modular blanket with gas cooled liquid lithium

This paper is a part of a study which aims to assess the feasibility of a demonstration Tokamak fusion reactor, relying on already available technologies. A modular design of the blanket, carried out in stainless steel and liquid lithium, is described. This blanket contains a helium heat exchange system submitted to low stresses under thermal transients. Neutronic and thermohydraulic calculations are reported. They show that under these conditions it is possible to design a blanket that provides a sufficient tritium amount to feed the reactor