Thermal hydraulic characteristic testing device and method for tritium blowing helium of breeding blanket pebble bed of fusion reactor

Abstract

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.

Description

technical field [0001] The invention relates to a fusion reactor breeding cladding pebble bed blowing tritium helium gas thermal-hydraulic characteristic experiment device and method, belonging to the field of thermal-hydraulics of advanced nuclear reactors. Background technique [0002] The thermonuclear reaction between the solid-state breeding cladding pebble bed of fusion reactor and the fission fuel pebble bed of the fourth-generation high-temperature gas-cooled reactor and high-energy neutrons produces high-power-density nuclear heat, which requires a specified mass flow rate of coolant to flow to discharge nuclear heat. The circuit working fluid heat exchange is used for tritium production, power generation or heat supply. Since the main function of the fusion reactor solid-state breeding cladding pebble bed is to breed tritium, compared with the fission reactor, the high-energy neutrons (14.1MeV) produced by the fusion reactor plasma deuterium-tritium thermonuclear r...

AI Technical Summary

Problems solved by technology

[0005] The technical problem solved by the present invention is: to overcome the deficiencies of the prior art, to provide a fusion reactor breeding cladding pebble bed blowing tritium helium gas thermal hydraulic characteristics experiment device and method, to solve the fusion reactor cladding pebble bed thermal characteristics experiment It is difficult to obtain high power density nuclear heat, and it also avoids the use of distributed resistance wires or inserting electric heating rods between the metal balls of the pseudo-proliferator to simulate the internal heat source, resulting in uneven distribution of nuclear heat, limited power density, and no generation of metal balls themselves. Heat, heat-generating components will affect technical defects such as tritium-blowing helium flow and heat transfer

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