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Preparation method of nuclear power (U, Ti) O2 mixing ceramic fuel pellet

A technology of titanium oxide and fuel pellets, which is applied in the field of preparation of O2 ceramic fuel pellets for nuclear power, can solve the problems of uneven distribution of titanium, high sintering temperature, dust pollution, etc., and achieve good microstructure and reasonable grain length The effect of large and low sintering temperature

Active Publication Date: 2013-12-25
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
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Problems solved by technology

This method has the following disadvantages: first, it is easy to cause dust pollution and increase the radioactive risk of the staff; second, the two kinds of ceramic powders are mechanically mixed and pressed into pellets, which will easily cause uneven distribution of titanium and affect its microstructure and internal and external properties. 3. Pellets manufactured by powder metallurgy generally require a higher sintering temperature, which increases the cost of nuclear fuel manufacturing

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  • Preparation method of nuclear power (U, Ti) O2 mixing ceramic fuel pellet

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Embodiment 1

[0029] Such as figure 1 shown.

[0030] A method for preparing uranium-titanium oxide mixed ceramic fuel pellets for nuclear power, including a sol configuration process, the sol configuration process includes a uranium-containing sol configuration step, a titanium-containing sol configuration step, and a uranium-titanium mixed sol configuration step, and the steps are as follows:

[0031] Uranium-containing sol configuration steps: Take acid-deficient uranyl nitrate solution and mix evenly with urea and polyacryl alcohol to obtain uniform and transparent acid-deficient uranyl nitrate sol;

[0032] Titanium-containing sol configuration steps: uniformly mix nano-titanium oxide powder, deionized water and nitric acid solution to obtain a uniform and stable titanium-containing sol;

[0033] Uranium-titanium mixed sol configuration step: uniformly mix the acid-deficient uranyl nitrate sol in the uranium-containing sol configuration step with the titanium-containing sol solution in ...

Embodiment 2

[0036] This embodiment adds the following technical content on the basis of the embodiment above: in the uranium-containing sol configuration step, the volume of the acid-deficient uranyl nitrate solution is 226ml, the uranium content in it is: 505g / l; the urea content is 48.5 g; Polypropylene alcohol is 110g. In the present invention, only when the above-mentioned content is configured, the acid-deficient uranyl nitrate sol can be prepared evenly and well mixed.

[0037] In the uranium-containing sol configuration step, the uniform mixing method is: after cooling the acid-deficient uranyl nitrate solution with a uranium content of 505g / l and a volume of 226ml to below 5°C, slowly add 48.5g of urea and 110g of poly Propylene alcohol, wherein the addition time of urea is 3 to 5 minutes, and the addition time of polypropylene alcohol is 20 to 30 minutes, stirring while adding. In the present invention, the acid-deficient uranyl nitrate sol can be prepared evenly and well mixed ...

Embodiment 3

[0045] This embodiment adds the following technical content on the basis of the third embodiment.

[0046] Preferably, the specific steps of the heating and curing process are as follows: transfer the prepared titanium-containing acid-deficient uranyl nitrate composite sol into a heating container, and use a resistance heating furnace to gradually heat it, and stir properly during heating. The heating temperature is : 25-45°C, heating time is 5-10 minutes, after 5-10 minutes, the mixed sol in the crucible solidifies into a block sample that loses fluidity;

[0047] The specific steps of the calcination process are as follows: dry and calcine the bulk sample after the heating and curing process in a high-temperature oven to obtain a dry and calcined powder, add 1000-1500ml of water to the high-temperature oven, and the heating program for drying and calcination is: 200-250min from room temperature to To 400 ℃, keep warm for 100min;

[0048] The specific steps of the reduction ...

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Abstract

The invention discloses a preparation method of nuclear power (U, Ti) O2 mixing ceramic fuel pellet, wherein acid-lacking nitric acid uranyl solution, nanometer titanium oxide, urea and polypropylene glycol are taken as raw materials; sol preparation, heating and solidification in a crucible, drying, calcining, powdering, reduction and sintering are performed to obtain the (U, Ti) O2 nuclear fuel pellet. The prepared (U, Ti) O2 nuclear fuel pellet has the advantages of low sintering temperature, excellent microstructure, higher mechanical strength density and the like. The technological process comprises solution mixture preparation, heating and solidification in the crucible, drying, calcining, powdering, reduction, sintering and metallographic erosion.

Description

technical field [0001] The invention relates to (U,Ti)O for nuclear power 2 The preparation technology of ceramic fuel pellets is a preparation method of uranium-titanium oxide mixed ceramic fuel pellets for nuclear power. Background technique [0002] Nuclear fuel elements are the core and key of nuclear reactors, and their performance directly affects the safety, reliability, economy, operating performance and service life of the reactor. In order to improve the economy of nuclear power and ease the pressure of fuel handling and disposal, high burnup and long life are the long-term pursuit goals of nuclear power plant fuel elements. However, the Fukushima nuclear power plant accident caused by the Japanese earthquake and tsunami in 2011 put forward higher requirements for the development of nuclear power fuel elements, that is, they hope to have high inherent safety. Therefore, the development goal of the new generation and future nuclear power is to improve its inherent...

Claims

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Application Information

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IPC IPC(8): G21C21/02G21C21/06
CPCY02E30/30
Inventor 王辉尹昌耕黄华伟龙弟均解怀英
Owner NUCLEAR POWER INSTITUTE OF CHINA
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