The ESEFP TCP provides a platform for scientists and engineers to exchange information and further enhance the collaboration, coordinating international efforts to bridge the scientific and technical gaps between the International Thermonuclear Experimental Reactor (ITER) and DEMO (a proposed nuclear fusion power station that is intended to build upon the ITER experimental nuclear fusion reactor), and supporting governmental policies and raising awareness of fusion energy developments and potential to the general public.
The scope of the FM TCP covers materials needed to meet the requirements of structural, thermal management, fuel breeding and processing, and neutron economy of fusion systems. Relevance and application of the results of this work range from meeting the needs of existing plasma physics devices, through International Thermonuclear Experimental Reactor (ITER), and DEMO (a proposed nuclear fusion power station that is intended to build upon the ITER experimental nuclear fusion reactor) stages of fusion development, to the application of advanced materials in fully mature fusion power plants serving the base energy needs of society.
The NTFR TCP is a collaborative programme on the research and development of nuclear technology of fusion reactors, a priority area for fusion energy. The TCP focuses on technologies of components located close to the fusion plasma and subjected to high-energy neutron irradiation, in particular tritium production and processing, energy extraction, radiation shielding and components such as the first wall, blanket, shield and plasma facing components.
The PWI TCP conducts research to understand the phenomena of interaction between the plasma and the chamber walls and to develop relevant wall materials for applications in fusion power.
The RFP TCP aims to advance the development of fusion power through research on the Reversed Field Pinch (RFP) magnetic configuration. The three members of the RFP TCP co-ordinate RFP experiments, and can share equipment and computational tools, as well as supporting staff exchanges.
Created in 2007, the ST TCP aims to enhance the effectiveness and productivity of fusion energy science and technology by strengthening co-operation among spherical torus research programmes and facilities; contributing to and extending the scientific and technology database of toroidal confinement concepts to the spherical torus physics regime; and providing a scientific and technological basis for the successful development of fusion power using the spherical torus.
The strategic objective of the SH TCP is to improve the physics base of the Stellarator concept and to enhance the effectiveness and productivity of research by strengthening co-operation among member countries.
The CTP TCP supports the development of fusion energy by contributing to the physics basis of the International Thermonuclear Experimental Reactor (ITER), and DEMO (a proposed nuclear fusion power station that is intended to build upon the ITER experimental nuclear fusion reactor) design optimisation. The CTP TCP provides a forum for tokamak programmes of the ITER Members to co-ordinate tokamak research by carrying out scientific and technological exchanges, holding workshops and meetings for the purpose of advancing the tokamak concept in the context of fusion energy, and supporting ITER physics and technology needs.