A Fusion Reactor Breeding Cladding Pebble Bed Blowing Tritium Helium Thermal Hydraulic Characteristics Experimental Device and Method

Abstract

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.

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...

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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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