The invention discloses a thermal hydraulic characteristic testing device and method for
tritium blowing
helium of a breeding
blanket pebble bed of a fusion reactor. The thermal hydraulic characteristic testing device for the
tritium blowing
helium of the breeding
blanket pebble bed of the fusion reactor is mainly used for researching the flow and
heat transfer characteristics of the
tritium blowing
helium of the
solid breeding
blanket layer of the fusion reactor between breeding agent pebbles of the
pebble bed. The thermal hydraulic characteristic testing method includes that using a non-
contact type high-frequency induction power to heat quasi
metal breeding agent pebbles to simulate high-
power density nuclear heat generated by the breeding agent pebbles in the pebble bed, researching the thermal hydraulic characteristics of the pebble bed under changed tritium blowing
helium temperature, speed and pressure, breeding agent pebble arrangement mode, size and
power density and the like, measuring the temperature distribution of the breeding agent pebbles and pebble bed wall surface, and obtaining a
convection heat transfer correlation equation and a flow resistance relation to provide supports for testing and demonstrating the nuclear
heat transmission of the
neutron deposition in the pebble bed on the breeding agent pebbles and the tritium blowing helium flow and
heat transfer characteristics under laboratory conditions, verifying the feasibility of a
solid breeding blanket designing scheme and the
correctness of a numerical method and data, and researching and developing Chinese
solid experiment blanket modules of ITER.