An experimental device for the thermal and hydraulic characteristics of tritium-helium blown in a fusion reactor breeding blanket pebble bed is mainly used to study the flow and heat transfer characteristics of the fusion reactor solid-state breeding blanket blowing tritium-helium gas between the pebble bed breeder pellets. Use a non-contact high-frequency induction power supply to heat the quasi-breeder metal balls to simulate the high power density nuclear heat generated by the breeder balls in the pebble bed, carry out the temperature, speed, and pressure changes of tritium-helium blowing, and arrange the breeder balls Experimental research on the thermal-hydraulic characteristics of the pebble bed under the conditions of mode, size, and power density changes, measuring the temperature distribution of the proliferator pellets and the wall surface of the pebble bed, and obtaining the relational expression of the convective heat transfer criterion and the flow resistance relational expression, which is the laboratory condition The experiment demonstrates the nuclear heat transfer of neutrons deposited on the breeder pellets in the pebble bed and the flow and heat transfer characteristics of tritium-helium blowing, and verifies the feasibility of the solid-state breeder envelope design scheme, the correctness of the numerical method and the data, for Provide support for the research and development of ITER China's solid-state experimental cladding module.