Preparation method of dispersion fuel pellet with high uranium loading capacity

A technology for dispersing fuel and loading capacity, which is applied in the fields of reactor fuel material, greenhouse gas reduction, and nuclear power generation. Irradiation stability, prolongation of release time, effect of improving safety performance

Active Publication Date: 2018-07-27
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 lower the thermal conductivity of the fuel pellets, the higher the temperature of the fuel assembly during reactor operation. Under the irradiation environment, the thermal stress and the release of fission gas in the pellets will also increase, which will lead to deformation and cracking of the pellets, shortening the fuel consumption. Component life
In addition, the lower the thermal conductivity of the fuel pellets, the higher the energy storage of the fuel system, which will greatly reduce the safety margin of the reactor operation, especially in the event of a loss of coolant accident (Loss Of Coolant Accident, LOCA) , the energy stored in the fuel system cannot be released quickly, which will directly lead to a sharp rise in the temperature of the fuel system, creep and collapse of the pellets, meltdown of the core, and exposure of radioactive substances. If it is not effectively controlled, it will cause a serious nuclear accident
After the Fukushima nuclear accident in Japan, people began to realize that the defect of traditional uranium dioxide with low thermal conductivity has become a major safety hazard affecting the operation of nuclear power plants (R.O.Meyer, Nucl.Technol., 2006,155:293)

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0021] UO with a particle size of about 100nm 2 The fuel core material is mixed with 2wt.% pore-forming agent ammonium oxalate to obtain uniformly dispersed UO 2 Mixture powder; the mixed powder is pressed into a green body with a density of 60%, and then crushed into mixture particles with a particle size of about 1 mm, and then the mixture particles are put into a container for rolling, grinding and spheroidizing for 12 hours to obtain UO 2 Mixture pellets; put the mixture pellets into the roller for rolling coating, and then weigh the reinforcing phase SiC accounting for 10% of the total mass of the mixture pellets, and the reinforcing phase sintering aid Y accounting for 12% of the total mass of the reinforcing phase SiC 2 o 3 、Al 2 o 3 , SiO 2 (mass ratio 1:1:1), mixed and coated for 2 hours, to obtain the reinforced phase SiC in UO 2 The surface of the mixture pellets is evenly coated with UO 2 @SiC core-shell structure wraps the sphere.

[0022] Will get UO 2 @S...

Embodiment 2

[0024] Mix the UC fuel core material with a particle size of about 500nm and 5wt.% pore-forming agent Akewax to obtain a uniformly dispersed UC mixture powder; press the mixed powder into a green body with a density of 40%, and then crush it into a particle size of about 2mm mixture particles, and then put the mixture particles in a container for rolling and grinding for 5 hours to obtain UC mixture pellets; put the mixture pellets into the roller for rolling coating, and then weigh 15% of the total mass of the mixture pellets. % reinforcement phase ZrC, and reinforcement phase sintering aid MoSi accounting for 20% of the total mass of reinforcement phase ZrC 2 , mixed and coated for 0.5 hours, and the reinforcing phase ZrC was uniformly coated on the surface of the UC mixture spheres, and the UC@ZrC core-shell structure coated spheres were obtained.

[0025]Put the obtained UC@ZrC core-shell structure-coated ball into a special graphite mold for spark plasma sintering for spa...

Embodiment 3

[0027] Mix the UN fuel core material with a particle size of about 5 μm and 0.1wt.% pore-forming agent ammonium oxalate to obtain a uniformly dispersed UN mixture powder; press the mixed powder into a green body with a density of 80%, and then crush it into a particle size of about 0.5mm mixture particles, and then put the mixture particles into the container for 18 hours of rolling grinding balls to obtain the UN mixture pellets; put the mixture pellets into the roller for rolling coating, and then weigh the total mass of the mixture pellets 5% reinforcement phase SiC, and reinforcement phase sintering aid Y accounting for 5% of the total mass of reinforcement phase SiC 2 o 3 、Al 2 o 3 (mass ratio 1:1), mixed and coated for 3 hours to obtain a UN@SiC core-shell structure coated sphere uniformly coated with the reinforcing phase SiC on the surface of the UN mixture sphere.

[0028] Put the obtained UN@SiC core-shell structure coated ball into a special graphite mold for spa...

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Abstract

The invention discloses a preparation method of a dispersion fuel pellet with high uranium loading capacity, which comprises the steps of firstly adopting means such as pelleting, self-grinding balling and rolling coating to realize the balling of a uranium-based fuel and the coating with a reinforcing phase, then performing high temperature plasma sintering on a coated ball to obtain the uranium-based fuel pellet; forming a large amount of pores in a core pellet of the fuel by utilizing the volatilization of a pore-forming agent under high temperature, then promoting the low-temperature rapiddensification sintering of the reinforcing phase by combining the high temperature plasma sintering technology and a sintering aid, thus obtaining the dispersion fuel pellet with high uranium loadingcapacity, wherein the dispersion fuel pellet has a special core-shell structure in which the compact reinforcing phase coats the porous fuel core pellet, and the special core-shell structure is loosein the interior and compact in the exterior. The method has the advantages that the preparation is simple and the preparation cost is low, can be used for the scale production of the uranium-based fuel pellet; the uranium-based fuel pellet prepared by the method has the advantages of high thermal conductivity, high safety, high uranium loading capacity and high economy.

Description

technical field [0001] The invention relates to a preparation method of high uranium loading dispersed fuel pellets. Background technique [0002] Uranium dioxide (UO 2 ) has the advantages of low neutron capture cross section, radiation stability, high melting point, good corrosion resistance to coolant water, and good compatibility with cladding materials, and is the most widely used nuclear fuel material in the nuclear industry . However, its thermal conductivity is the lowest among all nuclear fuel materials (metal type, carbide, nitride). Thermal conductivity is one of the most important thermophysical properties of nuclear fuel, which directly determines the performance of the fuel system in the nuclear reactor. The lower the thermal conductivity of the fuel pellets, the higher the temperature of the fuel assembly during reactor operation. Under the irradiation environment, the thermal stress and the release of fission gas in the pellets will also increase, which wil...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/64
CPCG21C3/64Y02E30/30
Inventor 杨振亮李冰清高瑞褚明福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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