Liquid Fuel Molten Salt Reactor with Graphite Ball as Moderator and Graphite Ball Replacement Method

Abstract

The invention discloses a liquid fuel molten salt stack using graphite balls as moderators and a graphite ball replacement method. The liquid fuel molten salt reactor using graphite balls as moderators includes a stack of core barrels and a fuel area arranged in the core barrels; the fuel area includes a mixing area of ​​the upper graphite balls and the fuel salt, and The pure fuel salt area in the lower layer; the core barrel is provided with a goal port at the bottom and a ball outlet port at the top, and the goal port is used to provide the fuel area with a goal channel for the graphite balls, The ball outlet is used to provide a ball outlet channel for discharging the graphite balls from the fuel zone; the volume percentage of the pure fuel salt region in the fuel zone is more than 2%. In the present invention, the graphite moderator can be replaced under non-stop conditions by replacing the graphite balls online, which reduces the need for shutdown, prolongs the life of the reactor core, and has high operating efficiency; and the graphite ball replacement process does not require external force. , The equipment is simple and the operation is simple.

Description

technical field [0001] The invention relates to a liquid fuel molten salt pile using graphite balls as a moderator and a method for replacing graphite balls. Background technique [0002] As the only liquid fuel reactor in the fourth-generation nuclear energy system, the molten salt reactor uses liquid fuel salt as the main coolant, works at high temperature and normal pressure, and has high safety, sustainable development, nuclear proliferation resistance and practicality. Adaptable to power generation, comprehensive utilization of nuclear energy and modular advanced reactors. In terms of fuel, unlike traditional solid fuel reactors, liquid fuel molten salt reactors do not require special solid fuel assemblies, but uniformly melt nuclear fuels such as uranium and thorium in liquid carrier salt. In terms of moderators, nuclear-grade graphite is usually selected as the moderator for liquid fuel molten salt reactors in the technical field. The liquid fuel molten salt reactor...

AI Technical Summary

Problems solved by technology

[0006] The technical problem to be solved by the present invention is to provide a liquid fuel molten salt moderator using graphite balls as a moderator in order to overcome the need to shut down and replace the graphite moderator in the core of the existing liquid fuel molten salt reactor or the complicated operation required for replacement. Salt pile and graphite ball replacement method

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