A conceptual design of a helium-cooled blanket for the NET double null plasma configuration with a neutron wall load of 1 MW/m2 and 600 MW fusion power is presented. The outboard blanket is made up of self-supporting canisters containing the beryllium multiplier in form of plates. The 6 mm wide slits between the plates contain a bed of 0.5 mm Li4SiO4 pebbles. The helium purge flow at 0.1 MPa carries away the tritium produced in the bed. The first wall of stainless steel and with a graphite tile protection is cooled by toroidally running helium tubes. The inboard blanket is made up of a similar structure, however the helium coolant tubes run in the poloidal direction to allow for more breeding material in the narrow space available. The divertors are composed of TZM elements cooled by helium. The outboard first wall and blanket are cooled by helium at 6 MPa, (inlet temperature = 200 °C outlet temperature = 450 °C), while the divertor and the inboard first wall are cooled in series by helium at 11.5 MPa and the inboard blanket by helium at 8 MPa. The calculated temperatures and stresses in blanket, first wall and divertor, appear to be acceptable. Based on the LISA-2 experiments the tritium blanket inventory is about 400 g. The daily tritium production is 96 g and the three-dimensional real tritium breeding ratio is 1.04 for a 6Li enrichment of 90%.