A dual-cladding fuel element with enhanced moderating power

Abstract

The invention belongs to the technical field of nuclear reactor fuel elements, and particularly relates to a dual-cladding fuel element with enhanced moderating power, which comprises an upper end plug, air cavity springs A, inner cladding, an air cavity spring B, outer cladding, a plurality of core blocks A, a plurality of core blocks B and a lower end plug, wherein the plurality of core blocks Aare stacked at the lower end in the inner cladding; an inner cladding fission gas cavity is formed above the upper parts of the core blocks A; one end of the inner cladding fission gas cavity is separated from the core blocks A through the gas cavity spring A, and the other end of the inner cladding fission gas cavity is also provided with a gas cavity spring A; the outer wall of the inner cladding is sleeved with the outer cladding; the plurality of core blocks B are stacked between the outer wall of the inner cladding and the inner wall of the outer cladding from bottom to top; the air cavity spring B is arranged above the upper parts of the core blocks B; the upper end plug is in positioning connection with the tops of the inner cladding and the outer cladding; the lower end plug is welded with the bottoms of the inner cladding and the outer cladding; the materials of the core blocks A and the core blocks B are combined in the form of a fission material-moderating material or a moderating material-fission material.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor fuel elements, and in particular relates to a double-clad fuel element with enhanced moderation capability. Background technique [0002] In order to improve heat exchange efficiency, many new nuclear reactor designs choose coolants with higher applicable temperature and stronger heat transfer capabilities, such as supercritical carbon dioxide, alkali metal sodium, potassium, lead-bismuth, etc. The coolant does not have a moderating effect. The reactor is physically designed as a fast neutron reactor. In order to meet the design requirements of criticality and core miniaturization, the reactor has a large amount of uranium and a high enrichment degree of uranium (more than 40%). In order to reduce the uranium load, reduce the fuel enrichment requirement, and improve the economy of the new reactor, moderator materials can be added to the core, and the reactor can be designed as a thermal n...

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Problems solved by technology

[0004] The purpose of the present invention is to design a double-clad fuel element with enhanced moderation capability in view of the deficiencies of the existing technology, which is used to solve the problem that water cannot be used as a moderator under high temperature in the prior art, and the reactor core has a large amount of uranium and fuel enrichment The technical problem of large core volume caused by high density

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