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Flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets

A fuel pellet, zirconium hydride technology, applied in the direction of moderator/core structure, nuclear power generation, climate sustainability, etc., can solve the problems of complex process, low density, high process difficulty, etc., and achieve short duration , The effect of shortening the flash sintering time and uniform distribution of the two phases

Active Publication Date: 2021-02-26
UNIV OF SCI & TECH BEIJING
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] The purpose of the present invention is to address the deficiencies of the prior art, to provide a flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets, which is used to solve the problem of preparing uranium-zirconium hydride by traditional sintering methods in the prior art Or technical defects such as low density of samples on uranium-yttrium hydride fuel pellets, time-consuming, energy-consuming, complicated process and difficult process

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  • Flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets

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Embodiment 1

[0035] This embodiment is uranium-zirconium hydride (U-ZrH x ) is prepared by flash sintering of fuel pellets, wherein the mass fraction of uranium 235 is 10%, and the design hydrogen zirconium ratio x is 1.43. First, uranium-zirconium alloy ingots are obtained by melting and casting according to the designed composition; then, the obtained ingots are subjected to appropriate hydrogenation treatment in a hydrogenation device to prepare uranium-zirconium hydride (U-ZrH x ) block fuel; then the obtained uranium-zirconium hydride block fuel is mechanically crushed, and further ball milled and sieved to make uranium-zirconium hydride powder with a certain particle size, which is used as a sintering raw material for standby; then weigh about 1g of powder raw material , and directly loosely load it into a flash sintering mold with an inner diameter of 10mm. After the powder raw material and electrodes are loaded, apply a pressure of 100MPa to the powder green body, and set the outpu...

Embodiment 2

[0037] This embodiment is uranium-zirconium hydride (U-ZrH x ) is prepared by flash sintering of fuel pellets, wherein the mass fraction of uranium 235 is 30%, and the design hydrogen zirconium ratio x is 1.57. First, uranium-zirconium alloy ingots are obtained by melting and casting according to the designed composition; then, the obtained ingots are subjected to appropriate hydrogenation treatment in a hydrogenation device to prepare uranium-zirconium hydride (U-ZrH x ) block fuel; then the obtained uranium-zirconium hydride block fuel is mechanically crushed, and further ball milled and sieved to make uranium-zirconium hydride powder with a certain particle size, which is used as a sintering raw material for standby; then weigh about 1g of powder raw material , and directly loosely load it into a flash sintering mold with an inner diameter of 10mm. After the powder raw materials and electrodes are loaded, apply a pressure of 250MPa to the powder green body, and set the outp...

Embodiment 3

[0039] This embodiment is uranium-zirconium hydride (U-ZrH x ) is prepared by flash sintering of fuel pellets, wherein the mass fraction of uranium 235 is 60%, and the design hydrogen zirconium ratio x is 1.71. First, uranium-zirconium alloy ingots are obtained by melting and casting according to the designed composition; then, the obtained ingots are subjected to appropriate hydrogenation treatment in a hydrogenation device to prepare uranium-zirconium hydride (U-ZrH x ) block fuel; then the obtained uranium-zirconium hydride block fuel is mechanically crushed, and further ball milled and sieved to make uranium-zirconium hydride powder with a certain particle size, which is used as a sintering raw material for standby; then weigh about 1g of powder raw material , and directly loosely load it into a flash sintering mold with an inner diameter of 10mm. After the powder raw materials and electrodes are loaded, apply a pressure of 500MPa to the powder green body, and set the outp...

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Abstract

The invention belongs to the technical field of nuclear reactor fuel elements, and particularly relates to a flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydridefuel pellets. Firstly, uranium-zirconium hydride or uranium-yttrium hydride powder with a certain particle size is prepared through smelting, casting, hydrogenation, crushing, ball milling and screening; and then powder raw materials are directly and loosely loaded into a flash sintering mold; flash sintering is conducted from the room temperature; and the uranium-zirconium hydride (U-ZrHx) or uranium-yttrium hydride (U-YHx) fuel pellet with the density close to the theoretical density can be obtained within 60 s. According to the flash sintering preparation method of the uranium-zirconium hydride and uranium-yttrium hydride fuel pellets, the technical defects of low density, time consumption, energy consumption, complex process and the like of the sample on the uranium-zirconium hydrideor uranium-yttrium hydride fuel pellet prepared by a traditional sintering method are overcome; the requirements on the ingot casting hydrogenation process are reduced, and the production cost is reduced while the product quality is improved; and the flash sintering preparation method of the uranium-zirconium hydride and uranium-yttrium hydride fuel pellets is a high-flux preparation means of thenuclear fuel pellet.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor fuel elements, in particular to a preparation method for flash sintering of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets. [0002] technical background [0003] Commonly used moderator materials include hydrogen-containing materials (light water, heavy water, certain organic substances and metal hydrides), beryllium (metals, oxides) and graphite. h 2 O is widely used as a moderator in light water reactors, but its use at a temperature higher than 400 °C has extremely high pressure requirements on the reactor. Therefore, H 2 O is not suitable as a high temperature moderator. Graphite can be used in high-temperature piles in non-oxidizing atmospheres, but its moderation ability is poor, so its use is greatly limited. Beryllium and beryllium oxide can also be used as moderators, and their moderation ability is better than that of graphite, but beryllium is highly toxi...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C1/05C22C28/00C22C29/00B22F3/105G21C5/12
CPCB22F3/105C22C1/05C22C28/00C22C29/005G21C5/12Y02E30/30
Inventor 张新房梁艺涵
Owner UNIV OF SCI & TECH BEIJING
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