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Preparation method of enhanced UO2 nuclear fuel pellet

A nuclear fuel and enhanced technology, which is applied in nuclear engineering, nuclear power generation, manufacturing reactors, etc., can solve the problems of large pellet grains, achieve scientific design, improve capacity, and meet technical requirements

Inactive Publication Date: 2019-06-18
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] Therefore, providing an enhanced UO 2 The preparation method of nuclear fuel pellets has simple process, convenient operation, large crystal grains of the obtained pellets, high thermal conductivity, and can effectively improve safety performance, which has become an urgent problem to be solved by those skilled in the art

Method used

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  • Preparation method of enhanced UO2 nuclear fuel pellet
  • Preparation method of enhanced UO2 nuclear fuel pellet
  • Preparation method of enhanced UO2 nuclear fuel pellet

Examples

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Embodiment 1

[0039] This embodiment provides the enhanced UO of the present invention 2 A method for preparing nuclear fuel pellets, specifically:

[0040] UO with a particle size of 50nm 2 The powder was mixed with 0.05wt.% of the reinforcing phase TiC, 0.05wt.% of the lubricant zinc stearate for 24 hours to obtain UO 2 Mixture powder with TiC. Press it into UO under 400MPa pressure with powder metallurgy pre-pressing mold 2 - TiC mixture pre-compacts. The pre-press is crushed and sieved to obtain UO with a particle size of 200 mesh 2 - TiC composite particles. Put the composite particles into spheroidization equipment for grinding and spheroidization for 8 hours to obtain UO with good sphericity 2 - TiC composite particles.

[0041] Spherified UO 2 -TiC composite particles are loaded into a powder metallurgy forming mold and pressed to a density of 5.8g / cm 3 nuclear fuel pellets. Put the obtained nuclear fuel pellet blank into an atmosphere sintering furnace, and carry out low-...

Embodiment 2

[0044] This embodiment provides the enhanced UO of the present invention 2 A method for preparing nuclear fuel pellets, specifically:

[0045] UO with a particle size of 5 μm 2 The powder was mixed with 1.5wt.% reinforcing phase VC, 0.2wt.% lubricant Akewax for 18 hours to obtain UO 2 Mixture powder with VC. Press it into UO with a cold isostatic press under a pressure of 500MPa 2 -VC mixture pre-compact. The pre-press is crushed and sieved to obtain UO with a particle size of 100 mesh 2 -VC composite particles. Put the composite particles into the spheroidization equipment for grinding and spheroidizing for 12 hours to obtain UO with good sphericity 2 - VC complex particles.

[0046] Spherified UO 2 -VC composite particles are loaded into powder metallurgy forming molds and pressed to a density of 6.5g / cm 3 nuclear fuel pellets. Put the obtained nuclear fuel pellet blank into an atmosphere sintering furnace, carry out low-temperature degreasing and high-temperature ...

Embodiment 3

[0048] This embodiment provides the enhanced UO of the present invention 2 A method for preparing nuclear fuel pellets, specifically:

[0049] UO with a particle size of 500 μm 2 powder with 0.5wt.% reinforcing phase Cr 3 C 2 , 0.5wt.% lubricant Akewax was mixed for 6 hours to obtain UO 2 with Cr 3 C 2 mixture powder. Press it into UO under 50MPa pressure with powder metallurgy pre-pressing mold 2 -Cr 3 C 2 The mixture is pre-compacted. The pre-compact was crushed and sieved to obtain UO with a particle size of 20 mesh 2 -Cr 3 C 2 Composite particles. Put the composite particles into spheroidization equipment for grinding and spheroidization for 1 hour to obtain UO with good sphericity 2 -Cr 3 C 2 Composite particles.

[0050] Spherified UO 2 -Cr 3 C 2 The composite particles are loaded into a powder metallurgy forming mold and pressed to a density of 5.0g / cm 3 nuclear fuel pellets. Put the obtained nuclear fuel pellet blank into an atmosphere sintering f...

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Abstract

The invention discloses a preparation method of an enhanced UO2 nuclear fuel pellet to solve the problems of rapid degrease of the thermal conductivity at a high temperature and rapid weakening of thegaseous fission product retention capacity of UO2 fuel pellets in the prior art. The preparation method comprises the following steps: cold-pressing shaping of UO2-reinforcing phase compound particles having good sphericility to obtain a nuclear fuel pellet blank, and sintering of the nuclear fuel pellet then in an active atmosphere at a high temperature to obtain the enhanced UO2 nuclear fuel pellet. The UO2-reinforcing phase compound particles are prepared from UO2 powder, a reinforcing phase and a lubricant; and the use amount of the reinforcing phase is 0.05-5% of the weight of the UO2 powder. The method is simple, and is scientifically designed; and the thermal conductivity at a high temperature and the gaseous fission product retention capacity of the enhanced UO2 fuel pellet are greatly higher than those of the existing UO2 fuel pellets.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel, in particular to an enhanced UO 2 Method for preparing nuclear fuel pellets. Background technique [0002] Uranium dioxide (UO 2 ) is currently the most widely used nuclear fuel material in commercial nuclear reactors. UO 2 It has a series of advantages, such as high neutron melting point, radiation stability, low capture cross section, good corrosion resistance to coolant water, good compatibility with cladding materials, etc. However, with the continuous improvement of the nuclear industry's safety requirements for nuclear fuel systems, the problems of low high-temperature thermal conductivity and weak fission product holding capacity have become more and more serious. In accident conditions where coolant is lost, conventional UO 2 The thermal conductivity of the fuel pellets will decline sharply, the temperature of the pellets will rise rapidly, the temperature gradient from the cent...

Claims

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Application Information

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IPC IPC(8): G21C21/02G21C21/10
CPCY02E30/30
Inventor 杨振亮李冰清高瑞褚明福张鹏程刘徐徐钟毅段丽美黄奇奇王志毅程亮刘朋闯严彪杰王昀
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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