Testing of the Nuclear In-Vessel Components: Requirements and Program

The development and testing of the nuclear in-vessel components in fusion reactor-relevant conditions is one of the major objectives of the Next European Torus (NET). The scope of nuclear testing in NET, the testing requirements, and program for the various breeding blanket concepts are defined and discussed with respect to thermal behavior, heat recovery, and tritium recovery. The relevance of NET testing for high neutron wall loads is also analyzed.