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A rod type fuel element using uranium-yttrium hydride fuel

A technology of fuel elements and yttrium hydride, which is applied in the direction of fuel elements, reactor fuel materials, and reduction of greenhouse gases. It can solve the problems of low decomposition temperature, high hydrogen release rate, and unsuitable use of reactors, so as to simplify the core and improve uniformity. , Improve the effect of economy and safety

Active Publication Date: 2022-05-20
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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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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  • A rod type fuel element using uranium-yttrium hydride fuel
  • A rod type fuel element using uranium-yttrium hydride fuel
  • A rod type fuel element using uranium-yttrium hydride fuel

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Embodiment Construction

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

[0028] A rod-shaped 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, a fuel core Block coating 7 and lower end plug 8; the top of the cladding tube 2 is positioned and fixedly connected to the upper end plug 1; the interior of the lower end of the cladding tube 2 stacks several fuel pellets 6 sequentially from bottom to top, and forms a pellet stack, The upper and lower ends of the stack of core blocks are provided with cushion blocks 5, and the upper part of the cushion block 5 at the upper end of the stack of core blocks is provided with a cladding fission gas air cavity; the upper and lower ends of the cladding fission gas air cavity are provided with There is an air cavity spring 4; the air cavity spring 4 a...

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Abstract

The invention belongs to the technical field of nuclear reactor fuel elements, and in particular relates to a rod-type fuel element using uranium-yttrium hydride fuel, including: an upper end plug, a cladding tube, an inner coating of the cladding tube, an air cavity spring, a pad, several fuel pellets, fuel pellet coating and lower end plug; the top of the cladding tube is positioned and fixedly connected to the upper end plug; inside the lower end of the cladding tube, several fuel pellets 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, and the upper part of the pad 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 provided with Air cavity spring; the air cavity spring at the lower end of the cladding fission gas cavity is in contact with the spacer at the upper end of the pellet stack; the gas cavity spring at the upper end of the cladding fission gas cavity is in contact with the upper end plug; the cladding tube The bottom is welded to the lower end plug; the fuel pellet material is 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-shaped 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 temperature, the coolant can no longer use water with moderating ability or heavy water, but use coolant with higher temperature and stronger heat transfer ability, such as supercritical carbon dioxide, alkali metal sodium, potassium, lead and bismuth, etc. At this time, since the coolant cannot be used as a moderator, the reactor is physically designed as a fast neutron reactor. The fast neutron fission cross section is small, resulting in a large amount of uranium, and the enrichment of uranium 235 is required to be high. [0003] In order to reduce the amount of uranium in the core, reduce the requiremen...

Claims

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Application Information

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Patent Type & Authority Patents(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