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A blanket concept made of SiCfISiC composite and utilizing Flibe as coolant and tritium breeder has been developed and integrated with the magnetic intervention system. To achieve tritium self-sufficiency, a 1 cm thick Be insert is utilized in the first wall coolant channel. All magnet, vacuum vessel, and personnel shielding requirements can be satisfied. The nuclear performance parameters of this blanket were compared to those of a lithium-lead blanket in two chamber core configurations. Because of the lighter blanket and shield weight that needs to be supported, the higher thermal power, and the lower electrical conductivity, the Flibe blanket option is particularly well suited for a laser fusion power plant with magnetic intervention.

A conceptually simple first wall (FW) and blanket design for an inertial fusion system based on utilizing mobile FW tiles is presented. Using these tiles that are periodically removed, annealed, and reinstalled, tritium retention and surface erosion concerns for inertial fusion FW could be mitigated. A conceptual configuration has been developed with consideration for laser beam port accommodation and a simple tile insertion and removal scheme. Tritium self-sufficiency can be achieved with a variety of options. The current preferred design option utilizes liquid Li breeder that serves also as coolant for both the FW tiles and blanket with ferritic steel structural material. Thermal analysis for the carbon fiber composite FW tiles in the HAPL nuclear environment indicates that the maximum temperature will be ~1300°C.