AbstractThe progress in the design and development of the first wall (FW) and divertor plates (DP) for the Next European Torus (NET) are summarized, highlighting the assumed main operating conditions, material choices, design options and their analysis as well as associated manufacturing studies and the ongoing testing programme.As plasma facing armor on both FW and DP, carbon based materials will be used at least during the initial physics phase due to their good performance in current tokamaks in respect to impurity control and disruption resistance.For the FW structure in water cooled austenitic steel, with radiation cooled armor adequate thermo-mechanical performance is predicted allowing peak heat fluxes of up to 0.8 MW/M2 at 2×104 long duration burn pulses.For divertor concepts with the armor attached by brazing to a water cooled heatsink, the peak heat flux is about 10 MW/M2. However, the main critical issue for the DP is the lifetime which is critically limited by erosion. The demonstration of the basic feasibility of FW and DP design is in progress via manufacture and thermo-mechanical testing of prototypical mock-ups.