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Preparation method of MAX-phase-imitating accident fault-tolerant nuclear fuel pellet

A nuclear fuel and accident technology, applied in fuel elements, nuclear power generation, climate sustainability, etc., can solve the problems of nuclear power plant safety hazards, fission gas release, steep temperature gradient of fuel pellets, etc., to achieve process stability improvement and cost reduction Effect

Active Publication Date: 2017-07-07
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The disadvantage is that the thermal conductivity is low, and the temperature gradient inside the fuel pellet is steep, which can easily lead to problems such as large internal thermal stress inside the pellet and the release of fission gas, which poses hidden dangers to the safety of nuclear power plants.
Its shortcomings are mainly that the radiation swelling is more serious, the anti-oxidation performance is insufficient, and the plasticity is much lower than that of UO. 2 , the preparation process is complex
[0003] It can be seen that the existing nuclear fuel designs have their own advantages and disadvantages, and there is room for improvement

Method used

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  • Preparation method of MAX-phase-imitating accident fault-tolerant nuclear fuel pellet
  • Preparation method of MAX-phase-imitating accident fault-tolerant nuclear fuel pellet

Examples

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Effect test

example 1

[0025] (1) Take the following raw materials in mass percentage: 40 μm uranium dioxide 70wt.%, 20 μm silicon 12wt.%, 20 μm graphite powder 12wt.%, zinc stearate 0.1wt.%, 10 μm TiO 2 5.9wt.%; after wet mixing the above powder in ethanol for 24 hours, take out the powder after drying;

[0026] (2) Prepare U by hot pressing sintering process 3 Si 2 C 2 : Put the powder in a graphite mold and vacuumize to 1.0×10 -3 Pa, the temperature is raised to 1300°C at 20°C / min, and then a pressure of 100MPa is applied and kept for 4 hours to obtain U 3 Si 2 C 2 ;

[0027] (3) Processing and forming: to be U 3 Si 2 C 2 After cooling, it is taken out and processed to the required shape and size, which is the fault-tolerant nuclear fuel pellet imitating the MAX phase.

[0028] U prepared by this method 3 Si 2 C 2 The density is 93.5%.

example 2

[0030] (1) Take the following raw materials in mass percentage: 20μm uranium dioxide 85wt.%, 5μm silicon carbide 7wt.%, 5μm flake graphite 7wt.%, zinc stearate 0.1wt.%, 1μm TiO 2 0.9wt.%; after wet mixing the above powder in ethanol for 12 hours, take out the powder after drying;

[0031] (2) Prepare U by hot pressing sintering process 3 Si 2 C 2 : Put the powder in a graphite mold and vacuumize to 1.1×10 -3 Pa, the temperature is raised to 1600°C at 5°C / min, and then a pressure of 20MPa is applied and kept for 4 hours to obtain U 3 Si 2 C 2 ;

[0032] (3) Processing and forming: to be U 3 Si 2 C 2 After cooling, it is taken out and processed to the required shape and size, which is the fault-tolerant nuclear fuel pellet imitating the MAX phase.

[0033] U prepared by this method 3 Si 2 C 2 The density is 97.3%.

example 3

[0035] (1) Take the following raw materials by mass percentage: 30 μm uranium dioxide 80wt.%, 10 μm silicon carbide 8wt.%, 10 μm carbon black 8wt.%, zinc stearate 0.1wt.%, 5 μm TiO 2 3.9wt.%; after wet mixing the above powder in ethanol for 18 hours, take out the powder after drying;

[0036] (2) Prepare U by hot pressing sintering process 3 Si 2 C 2 : Put the powder in a graphite mold and vacuumize to 0.9×10 -3 Pa, the temperature is raised to 1450°C at 10°C / min, and then a pressure of 60MPa is applied and kept for 2 hours to obtain U 3 Si 2 C 2 ;

[0037] (3) Processing and forming: to be U 3 Si 2 C 2 After cooling, it is taken out and processed to the required shape and size, which is the fault-tolerant nuclear fuel pellet imitating the MAX phase.

[0038] U prepared by this method 3 Si 2 C 2 The density is 95.1%.

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Abstract

The invention discloses a preparation method of a MAX-phase-imitating accident fault-tolerant nuclear fuel (U3Si2C2) pellet. U3Si2C2 is obtained by carrying out reactive sintering on uranium dioxide, a silicon-containing phase, carbon powder, a bonding agent and a sintering aid at a high temperature. Compared with U3Si2C2 prepared through traditional electric arc melting, U3Si2C2 prepared through the method has the advantages of low cost and good process stability. The nuclear fuel combines the excellent irradiation resistance, thermal conductance and oxidation resistance of the MAX phase and can be applied to traditional water reactors and a new generation of nuclear reactors.

Description

technical field [0001] The invention relates to a fault-tolerant nuclear fuel, in particular to a method for preparing a MAX-like fault-tolerant nuclear fuel pellet. Background technique [0002] After the Fukushima nuclear power plant accident in 2011, the safety of nuclear power has become a hot spot of widespread concern, and the research on high-performance accident-tolerant nuclear fuel has been pushed to a new level. The nuclear fuel pellets widely used in commercial nuclear power plants at this stage are UO 2 . UO 2 It has the advantages of high melting point, isotropy, good radiation stability, good corrosion resistance to water and good compatibility with cladding materials. The disadvantage is that the thermal conductivity is low, and the internal temperature gradient of the fuel pellet is steep, which easily leads to problems such as large internal thermal stress of the pellet and the release of fission gas, which poses hidden dangers to the safety of nuclear p...

Claims

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Application Information

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IPC IPC(8): C04B35/565C04B35/645C04B35/65G21C3/02
CPCC04B35/575C04B35/65C04B2235/3232C04B2235/424C04B2235/425C04B2235/48C04B2235/77G21C3/02Y02E30/30
Inventor 李冰清杨振亮高瑞贾建平唐浩刘徐徐钟毅段丽美黄奇奇王志毅
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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