Abstract
Abstract The concept of plasma facing elements (PFE) of a stationary fusion tokamak reactor based on the use of stagnant or slow-flowing liquid lithium enclosed in a capillary-porous structure which allows integrating the advantages of liquid metal with the possibility of its uniform distribution over the surface and ensuring a high stability under the influence of magnetohydrodynamic forces is considered in this study. Heat removal is provided by thermal conductivity through the PFE structure to the coolant. Development of the PFE design includes the creation and testing of a series of models of experimental devices such as a limiter and a divertor target with external systems of lithium refilling/change and heat removal designed for research in modeling conditions of bench installations and the T-11M tokamak. The paper presents the design and main parameters of such devices.