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.