The fuel-breeding blanket of a fusion reactor serves three essential functions: neutron shielding, energy conversion and recovery and fuel production.
This project aims to resolve the risk that conventional breeding blanket designs cannot secure sufficient plasma volume to achieve adequate fusion power output when reactor compactness is realized.

• We aim to realize a groundbreaking breeding blanket that can achieve fusion power and stability sufficient for commercial operation even in an ITER-scale reactor, along with the potential to innovatively reduce the overall tritium inventory of the entire plant.
• We are advancing the development of an advanced blanket (patent-pending idea - undisclosed) where thermal and neutron loading on the plasma-facing surface increases autonomously enhances heat removal performance and fuel breeding capability.
• With its high versatility, we will establish this blanket design as the global standard, thereby accelerating the worldwide societal deployment of deuterium–tritium (DT) fusion.