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Rod type fuel element adopting uranium-yttrium hydride fuel

A fuel element, yttrium hydride technology, applied in fuel elements, reactor fuel materials, reduction of greenhouse gases, etc., can solve the problems of unsuitable reactors, low decomposition temperature, high hydrogen release rate, and achieve improved economy and safety. Core, the effect of improving uniformity

Active Publication Date: 2020-06-12
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The object of the present invention is to aim at the deficiencies in the prior art, and design a rod-type fuel element using uranium-yttrium hydride fuel, which is used to solve the problem of high hydrogen release rate and low decomposition temperature of uranium-zirconium hydride fuel in the prior art at high temperature. Technical issues unsuitable for higher temperature reactors

Method used

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  • Rod type fuel element adopting uranium-yttrium hydride fuel
  • Rod type fuel element adopting uranium-yttrium hydride fuel
  • Rod type fuel element adopting uranium-yttrium hydride fuel

Examples

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Embodiment Construction

[0027] Below in conjunction with accompanying drawing and embodiment the present invention is further introduced:

[0028] A rod-type fuel element using uranium-yttrium hydride fuel, comprising: an upper end plug 1, a cladding tube 2, an inner coating of the cladding tube 3, an air cavity spring 4, a spacer 5, several fuel pellets 6, and a fuel core block coating 7 and lower end plug 8; the top of the cladding tube 2 is positioned and fixedly connected with the upper end plug 1; inside the lower end of the cladding tube 2, several fuel pellets 6 are sequentially stacked from bottom to top to form a stack of pellets, The upper and lower ends of the stack of pellets are provided with pads 5, and the upper part of the pad 5 at the upper end of the stack of pellets is provided with a cladding fission gas cavity; the upper and lower ends of the cladding fission gas cavity are set There is an air chamber spring 4; the air chamber spring 4 at the lower end of the cladding fission gas...

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Abstract

The invention belongs to the technical field of nuclear reactor fuel elements, and particularly relates to a rod type fuel element adopting uranium-yttrium hydride fuel, which comprises: an upper endplug, a cladding tube, a cladding tube inner coating, gas cavity springs, a cushion block, a plurality of fuel core blocks, a fuel core block coating and a lower end plug; the top of the cladding tubeis fixedly connected with the upper end plug in a positioning manner; a plurality of fuel pellets are sequentially stacked in the lower end of the cladding pipe from bottom to top to form a pellet stack; cushion blocks are arranged at the upper end and the lower end of the pellet stack; and a cladding fission gas cavity is formed in the upper portion of the cushion block at the upper end of the pellet stack. The gas cavity springs are arranged at the upper end and the lower end of the cladding fission gas cavity, wherein the gas cavity spring at the lower end of the cladding fission gas cavity is in contact with a cushion block at the upper end of the pellet stack and the gas cavity spring at the upper end of the cladding fission gas cavity is in contact with the upper end plug; the bottom of the cladding tube is welded with the lower end plug; and the fuel pellet is made of uranium-yttrium hydride U-YHx.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor fuel elements, in particular to a rod type fuel element using uranium-yttrium hydride fuel. Background technique [0002] Newer reactor designs require higher volumetric power densities and therefore higher operating temperatures to achieve higher heat transfer efficiencies. At high temperatures, the coolant cannot continue to use moderate water or heavy water, but coolants with higher applicable temperatures and stronger heat transfer capabilities are used, such as supercritical carbon dioxide, alkali metal sodium, potassium, lead bismuth, etc. At this time, because the coolant cannot be used as a moderator, the reactor is physically designed as a fast neutron reactor. The fast neutron fission section is small, resulting in a large amount of uranium, and the enrichment degree of uranium 235 is high. [0003] In order to reduce the uranium load in the core, reduce the requirement of uran...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/20G21C3/58
CPCG21C3/20G21C3/58Y02E30/30
Inventor 李权柴晓明黄永忠王金雨李文杰段振刚余红星彭诗念吕亮亮李垣明张卓华曾畅唐昌兵高士鑫路怀玉
Owner NUCLEAR POWER INSTITUTE OF CHINA