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A thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading and its preparation method

A technology of uranium dioxide and fuel pellets, which is applied in the field of reactor fission materials, can solve the problems that cannot meet the requirements of higher intrinsic safety of nuclear energy and the development of multi-application reactor types, and achieve scientific design, concise methods, and enhanced thermal conductivity. rate effect

Active Publication Date: 2021-09-28
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

Under the new trend of rapid development of nuclear energy and the requirement of higher intrinsic safety, uranium dioxide fuel can no longer meet the requirements of higher intrinsic safety of nuclear energy and the development of multi-application reactor types in the future.

Method used

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Examples

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Effect test

Embodiment 1

[0027] This embodiment discloses the preparation of a thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading of the present invention, specifically:

[0028] 1) Add uranium dioxide microspheres and uranium-molybdenum alloy powder in a volume ratio of 95:5, in which the volume ratio of uranium / molybdenum is 4.5:0.5, and add them to a nylon tank for dry mixing without adding any grinding media and grinding The ball is filled with high-purity argon for protection, the rotation speed is 280r / min, and the mixing time is 0.5h. Get a homogeneously mixed UO 2 - U-Mo compound.

[0029] 2) The UO obtained in step 1 2 -U-Mo mixture, put it into a graphite mold, and carry out spark plasma sintering densification, the sintering temperature is 900°C, the heating rate is 50°C / min, the holding time is 30min, the pressure is 80MPa, and the vacuum degree is 0.1 Pa. Then remove the film and size processing.

[0030] It has been determined that the the...

Embodiment 2

[0032] This embodiment discloses the preparation of a thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading of the present invention, specifically:

[0033] 1) Add uranium dioxide raw material powder, metal uranium powder and molybdenum powder in a volume ratio of 60:35:5 into a nylon tank, and fill it with high-purity argon gas for protection, and dry-mix at a speed of 150r / min. The feeding time is 12 hours, each rotation is 1 hour, and the interval is 0.5 hours, so that the forward and reverse cycles are obtained; uniformly mixed UO 2 - U-Mo compound.

[0034] 2) The UO obtained in step 1 2 -U-Mo mixture, put it into graphite mold, and carry out discharge plasma sintering densification, the sintering method is discharge plasma sintering, specifically: the sintering atmosphere is vacuum, the sintering temperature is 1400 °C, and the heating rate is 200°C / min, the holding time is 1min, the pressure is 30MPa, and the vacuum degree is 2...

Embodiment 3

[0037] This embodiment discloses the preparation of a thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading of the present invention, specifically:

[0038] 1) Put uranium dioxide raw material powder, metal uranium powder and molybdenum powder in a volume ratio of 85:13:2, add it into a nylon tank, and fill it with high-purity argon gas for protection, and carry out dry mixing at a speed of 200r / min. The feeding time is 8 hours, each rotation is 1 hour, and the interval is 0.5 hours, so that the forward and reverse cycles are obtained; a uniformly mixed UO2-U-Mo mixture is obtained.

[0039] 2) The UO obtained in step 1 2 -U-Mo mixture, put it into a hot-pressing mold, and carry out hot-pressing sintering as follows: the sintering atmosphere is vacuum, the sintering temperature is 1000°C, the heating rate is 5°C / min, the holding time is 4h, the pressure is 100MPa, the vacuum The degree is 50Pa. Then remove the film and size processing...

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Abstract

The invention discloses a thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading and a preparation method thereof. The uranium-molybdenum alloy phase is generated by the site reaction, and the fuel pellets after high-temperature sintering and densification are enhanced in the UO 2 In addition to the thermal conductivity of the fuel pellets, the uranium loading of the uranium dioxide pellets can be increased, and at the same time, the uranium loading can be increased in the form of a uranium-molybdenum alloy phase, which has higher radiation stability. Endowed with a certain mechanical processing performance, it can meet the design requirements of the reactor under higher fuel, and expand the application reactor type of the uranium dioxide-based fuel pellet. This improved thermal conductivity uranium dioxide-based fuel pellet with increased uranium loading can improve the inherent safety and economics of commercial pressurized water reactors, and can be applied to reactor types with higher burnup such as space reactors, row reactors, etc. Wave reactor, ADS system and other new reactors.

Description

technical field [0001] The invention belongs to the field of reactor fission materials, and in particular relates to a thermal conductivity-improved uranium dioxide-based fuel pellet with increased uranium loading and a preparation method thereof. Background technique [0002] With the development of the national economy and the improvement of people's living standards, China will face the problem of energy shortage. By 2050, China's energy gap will reach 1 billion tons of standard coal. The extensive use of carbon-based fuels by humans has become one of the important factors of environmental pollution. Accelerating the development of nuclear power is an important way to solve the above contradictions. Nuclear energy is gradually becoming an important part of future energy due to its unique advantages such as high energy density and no greenhouse gas emissions. The nuclear fission energy with mature technology is expected to provide guarantee for future energy demand and su...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C3/64G21C3/62G21C21/16
CPCG21C3/623G21C3/64G21C21/16Y02E30/30
Inventor 程亮张鹏程严彪杰王志毅高瑞杨振亮李冰清褚明福钟毅王昀黄奇奇
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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