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A kind of preparation method of uranium dioxide-graphene composite fuel pellet

A graphene composite and uranium dioxide technology, which is applied in the field of preparation of uranium dioxide-graphene-like composite fuel pellets, can solve the problems of fuel pellet uranium loading, pellet density reduction, and high doping amount. Achieve high thermal conductivity, simple process and high efficiency

Active Publication Date: 2022-05-13
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] However, the common disadvantages of the above-mentioned technologies include: first, the large amount of doping will lead to a significant decrease in the fuel pellet uranium loading and pellet density; second, the doped phase is in the UO 2 Uniform dispersion within the matrix

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0027] Example 1: Preparation of uranium dioxide-graphene-like composite fuel pellets

[0028] (1) Preparation of PAN-N,N-dimethylformamide (DMF) solution

[0029] Weigh 0.4g of PAN powder and 20ml of DMF solvent, pour the PAN powder into DMF and stir well, heat the container to 40°C to promote the dissolution of PAN until the PAN powder is completely dissolved in DMF.

[0030] (2) Preparation of UO 2 -PAN-DMF intermediate

[0031] Weigh UO 2 100g of powder (average particle size is 2 μm), poured into the PAN-DMF solution obtained in step (1), fully mixed and stirred to obtain UO 2 -PAN-DMF intermediate.

[0032] (3) Preparation of UO 2 -PAN mixed powder

[0033] The UO obtained in step (2) 2 - The PAN-DMF intermediate is vacuum evaporated, and the DMF is fully evaporated to dryness at 80°C to obtain UO 2 -PAN mixed powder.

[0034] (4) Preparation of fuel pellet green body

[0035] Take 10 g of the mixed powder obtained in step (3), place it in a forming mold, press...

Embodiment 2

[0038] Example 2: UO 2 -Analysis and detection of PAN mixed powder and uranium dioxide-graphene-like composite fuel pellets

[0039] With the UO that embodiment 1 prepares 2 -PAN mixed powder and uranium dioxide-graphene-like composite fuel pellets are tested as follows:

[0040] (1) Detection of powder specific surface area

[0041] According to GB / T 11847-2008 "BET Volumetric Method for Determination of Specific Surface Area of ​​Uranium Dioxide Powder", the raw material UO 2 Powder and prepared UO 2 -PAN mixed powder was tested for specific surface area, and the test result was 3.01m 2 / g, the latter is 3.79m 2 / g.

[0042] (2) Detection of powder oxygen uranium atomic ratio

[0043] According to GB / T 11842-89 "Thermogravimetric method for the determination of the atomic ratio of oxygen and uranium in uranium dioxide powder and pellets", the raw material UO 2 Powder and prepared UO 2 - The atomic ratio of oxygen and uranium in the mixed powder of PAN was detected, ...

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PUM

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Abstract

The invention belongs to the technical field of nuclear fuel preparation, and relates to a method for preparing uranium dioxide-graphene-like composite fuel pellets. The preparation method comprises the following steps: (1) dissolving polyacrylonitrile with a solvent, adding uranium dioxide powder, and mixing uniformly to obtain an intermediate; (2) evaporating the intermediate to remove the solvent to obtain uranium dioxide-polyacrylonitrile Mixed powder; (3) putting uranium dioxide-polyacrylonitrile mixed powder into a mold for cold press molding, demolding to obtain the fuel pellet green body; (4) sintering the fuel pellet green body under a reducing atmosphere, Obtain uranium dioxide-graphene-like composite fuel pellets. Utilizing the preparation method of the uranium dioxide-graphene-like composite fuel pellet of the present invention, a novel composite fuel pellet with high thermal conductivity can be prepared, thereby improving the economy and safety of a nuclear reactor during operation.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel preparation, and relates to a method for preparing uranium dioxide-graphene-like composite fuel pellets. Background technique [0002] UO 2 High melting point, low radiation swelling, therefore, worldwide, UO 2 Pellet-Zr cladding is the most important fuel system in commercial pressurized water reactors. But UO 2 low thermal conductivity, making UO 2 -The Zr fuel system produces a large temperature gradient during operation, which causes thermal stress in the pellets and reduces the thermal stability of the pellets. In extreme cases, the center temperature of the fuel pellets is too high, which may even cause cladding Breakage and core meltdown. [0003] Since the Fukushima nuclear accident in Japan, the development of advanced nuclear fuel, especially the development of nuclear fuel pellets with high thermal conductivity, has become a new hotspot in international research. [0004] A r...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C04B35/51C04B35/622C04B35/63G21C3/62G21C21/02
CPCC04B35/51C04B35/622C04B35/6303G21C3/623G21C21/02C04B2235/48C04B2235/5436C04B2235/5445C04B2235/602C04B2235/656C04B2235/6567C04B2235/6582C04B2235/9607Y02E30/30
Inventor 马浩然张燕朱礼洋杨志红杨素亮田国新郭波龙隋政冯海宁
Owner CHINA INSTITUTE OF ATOMIC ENERGY