Preparation method of metallic fuel pellet with high irradiation stability

A technology of fuel pellets and stability, which is applied in the field of preparation of metal-type fuel pellets, can solve problems such as swelling and deformation of metal-type nuclear fuel, and achieve good mechanical properties, resistance to radiation deformation, and good resistance to pulling and bending Effect

Active Publication Date: 2018-08-17
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

[0002] Relative to the UO most commonly used in commercial reactors 2 Fuel, metal-type nuclear fuel based on uranium-based alloys has the advantages of high uranium loading and high thermal conductivity, but due to the large degree of swelling and deformation of metal-type nuclear fuel under irradiation conditions, the use of this type of pellets in nuclear reactors is limited. application in

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0020] Step 1: Proportion raw materials as follows:

[0021] U-10M alloy powder, 5μm~100μm, 235 U enrichment 1-5%, 99vol%, silicon carbide particles, particle size 10nm-100nm, 1vol%, put the above powder in a nylon ball mill jar, add 3 times the mass of zirconia grinding balls, and mix for 24h.

[0022] Step 2, carry out sintering as follows:

[0023] The mixed powder is molded to obtain a fuel pellet green body. The forming pressure is 100Mpa. The green body is placed in an atmosphere sintering furnace for pressureless sintering. First, the temperature is raised to about 600 ° C at a rate of 5 to 10 ° C / min and kept for 0.5 h, then heat up to 1100°C at a rate of 1°C / min, hold for 2h, furnace cool, the atmosphere is an argon atmosphere, and the pressure is 10-50kPa.

[0024] Step 3: After cooling with the furnace, the sample is taken out and processed to the required shape and size.

Embodiment 2

[0026] Step 1: Proportion raw materials as follows:

[0027] U-10Zr alloy powder, 5μm~100μm, 235 U enrichment 1-5%, 99.9 vol%, SiC whiskers with a diameter of 20nm-200nm and a length of 5-20μm, 0.1vol%, put the above powder in a nylon ball mill jar, add 3 times the mass of zirconia Grind the balls and mix for 24h.

[0028] Step 2, carry out sintering as follows:

[0029] The mixed powder is molded to obtain a fuel pellet green body. The forming pressure is 300Mpa. The green body is placed in an atmosphere sintering furnace for pressureless sintering. First, the temperature is raised to about 500 ° C at a rate of 5 to 10 ° C / min, and the temperature is kept for 0.5 h. Heat up to 850°C at a rate of 1°C / min, hold for 1h, furnace cool, the atmosphere is vacuum, and the pressure is 5×10 -2 ~5×10 -1 Pa.

[0030] Step 3: After cooling with the furnace, the sample is taken out and processed to the required shape and size.

Embodiment 3

[0032] Step 1: Proportion raw materials as follows:

[0033] U 3 Si 2 Alloy powder, 5μm~100μm, 235 U enrichment 1-5%, 95vol%, carbon nanotubes with a diameter of 5nm-100nm and a length of 1-20μm, 5vol%, put the above powder in a nylon ball mill, add 3 times the mass of zirconia grinding balls , mixed for 24h.

[0034] Step 2, carry out sintering as follows:

[0035] The powder is placed in the designed graphite mold, and hot-pressed sintering is performed. The sintering process is as follows: raise the temperature to 800 °C at a rate of 1-20 °C / min and keep it for 1 h, while applying a sintering pressure of 20 MPa. Cold, sintering atmosphere is argon.

[0036] Step 3: After cooling with the furnace, the sample is taken out and processed to the required shape and size.

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PUM

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Abstract

The invention discloses a preparation method of a metallic fuel pellet with high irradiation stability. The preparation method comprises the following steps: firstly, mixing uranium-based alloy powderand a carbon-based nanomaterial according to the volume ratio of (99.9-99):(1-0.1), then, placing the mixture into a nylon ball milling tank, adding zirconia grinding balls of which the mass is 3 times as high as that of the mixture, and carrying out mixing for 24h to obtain a mixed powder; and secondly, carrying out pressureless sintering, hot pressed sintering, spark plasma sintering or flash sintering on the mixed powder, after heat preservation and pressure preservation, carrying out furnace cooling, taking out the cooled material, and then, processing and molding the cooled material to obtain the metallic fuel pellet. The metallic fuel pellet obtained by using the method has the advantages of high uranium loading capacity, high heat conductivity, good anti-irradiation properties, strong fission gas accommodating capacity and excellent mechanical properties and can be used as a novel nuclear fuel of a nuclear reactor.

Description

technical field [0001] The invention relates to a preparation method of a metal type fuel pellet with high radiation stability. Background technique [0002] Relative to the most commonly used UO in commercial reactors 2 Fuel, metal-type nuclear fuel based on uranium-based alloy has the advantages of high uranium loading and high thermal conductivity, but due to the large degree of swelling and deformation of metal-type nuclear fuel under irradiation conditions, it limits the use of this type of pellet in nuclear reactors. applications in . SUMMARY OF THE INVENTION [0003] The purpose of the present invention is to solve the above-mentioned technical problems, provide a preparation method of a metal type fuel pellet, improve the thermophysical properties, mechanical properties and radiation stability of the metal type fuel pellet, so that this type of pellet has Conditions applied in nuclear reactors. [0004] For achieving the above object, the technical scheme adopte...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/60G21C21/16
CPCG21C3/60G21C21/16Y02E30/30
Inventor 高瑞杨振亮李冰清褚明福唐浩钟毅刘徐徐段丽美黄奇奇王志毅
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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