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Anti-oxidation coating for nuclear fuel pellets and preparation method thereof

A nuclear fuel and anti-oxidation technology, applied in the direction of uranium dioxide, reactor fuel material, uranium oxide/hydroxide, etc., to achieve the effect of preventing oxidation

Active Publication Date: 2020-10-09
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The traditional process to prevent the surface oxidation of metal oxide nuclear fuel pellets is to plate nickel on the surface of nuclear fuel pellets, but this is only applicable if the nuclear fuel pellets are not considered to continue to be used. remove

Method used

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  • Anti-oxidation coating for nuclear fuel pellets and preparation method thereof

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Comparison scheme
Effect test

Embodiment 1

[0024] Embodiment 1: Preparation of nuclear fuel pellet anti-oxidation coating (1)

[0025] UO was prepared by the following steps 2 Antioxidant coatings for nuclear fuel pellets.

[0026] (1) Preparation of polycarbosilane solution

[0027] Take 10g of polycarbosilane (provided by National University of Defense Technology, molecular weight 1400-2000) and dissolve it in 100ml of petroleum ether. During the dissolution process, if necessary, heat it in a water bath to 40°C and stir. After the dissolution is complete, cool to room temperature and filter to obtain a polycarbosilane solution.

[0028] (2) Coating of polycarbosilane protective layer

[0029] The polycarbosilane solution was transferred to an argon-protected glove box, and the UO 2 The pellet is immersed in the polycarbosilane solution, taken out to dry, and repeated 4 times to complete the preparation of the polycarbosilane coating.

[0030] The anti-oxidation coating thus prepared has a thickness of 10-20 μm....

Embodiment 2

[0031] Embodiment 2: Preparation of nuclear fuel pellet anti-oxidation coating (two)

[0032] Utilize the method for following steps to prepare substoichiometric uranium dioxide (UO 2-x ) anti-oxidation coating of nuclear fuel pellets.

[0033] (1) Preparation of polycarbosilane solution

[0034] Take 30g of polycarbosilane (provided by National University of Defense Technology, molecular weight 1400-2000) and dissolve it in 100ml of cyclohexane. During the dissolution process, if necessary, heat it to 60°C in a water bath and stir. After the dissolution is complete, cool to room temperature and filter to obtain a polycarbosilane solution.

[0035] (2) Coating of polycarbosilane protective layer

[0036] The polycarbosilane solution was transferred to an argon-protected glove box, and substoichiometric uranium dioxide (UO 2-x ) The pellet is immersed in the polycarbosilane solution, taken out to dry, and repeated 3 times to complete the preparation of the polycarbosilane c...

Embodiment 3

[0038] Embodiment 3: Preparation of nuclear fuel pellet anti-oxidation coating (three)

[0039] The anti-oxidation coating of the MOX nuclear fuel pellets is prepared by the following steps.

[0040] (1) Preparation of polycarbosilane solution

[0041] Take 20g polycarbosilane (provided by National University of Defense Technology, molecular weight 1400-2000) and dissolve it in 100ml xylene. During the dissolution process, if necessary, heat it to 50°C in a water bath and stir. After the dissolution is complete, cool to room temperature and filter to obtain a polycarbosilane solution.

[0042] (2) Coating of polycarbosilane protective layer

[0043] Transfer the polycarbosilane solution to an argon-protected glove box, immerse the MOX pellet in the polycarbosilane solution, take it out to dry, and repeat 4 times to complete the preparation of the polycarbosilane coating.

[0044] The anti-oxidation coating thus prepared has a thickness of 40-60 μm.

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Abstract

The invention belongs to the technical field of nuclear fuel corrosion protection and relates to an anti-oxidation coating layer for a nuclear fuel pellet and a preparation method of the anti-oxidation coating layer. The anti-oxidation coating layer is positioned on the surface of the nuclear fuel pellet, and the composition of the anti-oxidation coating layer is polycarbosilane. The preparation method of the anti-oxidation coating layer sequentially comprises the following steps: (1) dissolving the polycarbosilane in a suitable solvent to form a polycarbosilane solution; (2) immersing the nuclear fuel pellet in the polycarbosilane solution, so that the polycarbosilane uniformly coats the nuclear fuel pellet; and (3) taking out the nuclear fuel pellet from the polycarbosilane solution andair-drying. By the utilization of the anti-oxidation coating layer for the nuclear fuel pellet and the preparation method of the anti-oxidation coating layer, the prepared anti-oxidation coating layernot only can effectively prevent the oxidation of the nuclear fuel pellet, but also cannot affect the composition and the performance of the nuclear fuel pellet in the processes of making and removing the coating layer.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel anti-corrosion, and relates to an anti-oxidation coating for nuclear fuel pellets and a preparation method thereof. Background technique [0002] Metal oxide nuclear fuels are widely used in nuclear reactors, among which uranium dioxide (UO 2 ) and mixed oxides (MOX) are typical representatives. Among the indicators for measuring metal oxide nuclear fuel pellets, the oxygen-to-metal ratio (O / M) is a crucial indicator, especially for substoichiometric uranium dioxide (UO 2-x ) fuel and uranium plutonium MOX fuel. [0003] However, metal oxide nuclear fuel pellets will inevitably come into contact with air or water during transport, storage and testing. Studies have shown that they will be oxidized by air (oxygen) or water during the process, which has great impact on metal oxide nuclear fuel pellets. The oxygen-to-metal ratio of the block has an important influence, and may even lead to an ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C3/58G21C21/16C01G43/025
CPCC01G43/025G21C3/58G21C21/16Y02E30/30
Inventor 魏国良尹邦跃
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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