UO2-metal fuel pellet and production method thereof

A metal fuel and manufacturing method technology, applied in the direction of manufacturing reactors, reactor fuel materials, nuclear power generation, etc., can solve problems affecting the ratio of oxygen to uranium

Inactive Publication Date: 2018-09-21
CHINA NUCLEAR POWER TECH RES INST CO LTD +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, distributed in UO 2 The metal M powder of the matrix will be mixed with UO during the sintering process 2 A displacement reduction reaction occurs to form metal M x+ ions, and solid solution in UO 2 matrix, which affects UO 2 Oxygen to uranium ratio of matrix

Method used

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  • UO2-metal fuel pellet and production method thereof
  • UO2-metal fuel pellet and production method thereof
  • UO2-metal fuel pellet and production method thereof

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0051] Weigh Cr with a particle size of 1 μm 2 o 3 Powder 0.5wt.%; the balance is UO with a particle size of 0.5μm 2 powder. Put each powder into a ball mill jar and mix evenly on a roller ball mill or a planetary ball mill. The mixed powder is compacted into a green body at a pressure of 100 MPa, and the formed green body has a radius of φ50 mm and a height of 20 mm. The green body is pre-fired in a high-temperature atmosphere furnace, the sintering temperature is 1500°C, and the holding time is 4h. The solid solution obtained after pre-calcination is crushed and sieved, and then the approximately spherical UO is obtained by self-grinding 2 Particles; at UO 2 Add 10wt.% Cr powder to the pellets and mix. Using compression molding method, the pressing pressure is 300MPa, and the UO 2 The particles are pressed into pellets; under an inert or reducing atmosphere, the pellets are densified by pressureless sintering at a sintering temperature of 1700°C to obtain fuel pellets...

Embodiment 2

[0055] Weigh MoO with a particle size of 1 μm 2 Powder 0.5wt.%; the balance is UO with a particle size of 0.5μm 2 powder. Put each powder into a ball mill jar and mix evenly on a roller ball mill or a planetary ball mill. The mixed powder is compacted into a green body at a pressure of 100 MPa, and the formed green body has a radius of φ50 mm and a height of 20 mm. The green body is pre-fired in a high-temperature atmosphere furnace, the sintering temperature is 1500°C, and the holding time is 4h. The solid solution obtained after pre-calcination is crushed and sieved, and then the approximately spherical UO is obtained by self-grinding 2 Particles; at UO 2 Add 10wt.% Mo powder to the pellets and mix. Using compression molding method, the pressing pressure is 300MPa, the UO mixed with Mo powder 2 The particles are pressed into pellets; under an inert or reducing atmosphere, the pellets are densified by pressureless sintering at a sintering temperature of 1700°C to obtain...

Embodiment 3

[0059] Weigh ZrO with a particle size of 1 μm 2 Powder 0.5wt.%; the balance is UO with a particle size of 0.5μm 2 powder. Put each powder into a ball mill jar and mix evenly on a roller ball mill or a planetary ball mill. The mixed powder is compacted into a green body at a pressure of 100 MPa, and the formed green body has a radius of φ50 mm and a height of 20 mm. The green body is pre-fired in a high-temperature atmosphere furnace, the sintering temperature is 1500°C, and the holding time is 4h. The solid solution obtained after pre-calcination is crushed and sieved, and then the approximately spherical UO is obtained by self-grinding 2 Particles; at UO 2 Add 10wt.% Zr powder to the pellets and mix. Using compression molding method, the pressing pressure is 300MPa, the UO mixed with Zr powder 2 The particles are pressed into pellets; under an inert or reducing atmosphere, the pellets are densified by pressureless sintering at a sintering temperature of 1700°C to obtain...

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Abstract

The invention discloses a UO2-metal fuel pellet and a production method thereof. The production method comprises the following steps: S1, weighing the following raw materials in mass percent: 0-2% ofCr2O3, 0-2% of MoO2, 0-2% of ZrO2 and the balance of UO2; S2, ball-milling and uniformly mixing the raw materials to form mixed powder; S3, pressing the mixed powder to form a billet, and performing high-temperature pre-sintering to obtain a solid solution; S4, crushing the solid solution, and performing sieving and ball milling to form granular mixture; S5, doping metal powder into the granular mixture, and performing mixing to ensure that the surface of each granule in the granular mixture is coated with the metal powder; and S6, performing compression molding on the granular mixture doped with the metal powder, and performing densification sintering to obtain the UO2-metal fuel pellet. The UO2-metal fuel pellet disclosed by the invention has the advantages that the thermal conductivityof the pellet is increased by 50% or above due to addition of the metal, the grain size of the pellet is increased, the core temperature of the pellet fuel in service is obviously reduced, the temperature gradient is reduced, the release of fission products of the pellet fuel is inhibited, and the performance of a fuel rod is enhanced.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel, in particular to a UO 2 -Metal fuel pellets and method for their manufacture. Background technique [0002] Thanks to UO 2 Ceramics have the advantages of high melting point, good stability, and good radiation performance. Most of the fuel elements of commercial nuclear reactors in the world use UO 2 Ceramics as fuel pellets. However, UO 2 The thermal conductivity of ceramics is low, and the fuel pellets form a large temperature gradient during service, and the core temperature reaches above 1500 °C. A large temperature gradient leads to thermal stress in the pellets, and a high temperature of the pellets increases the release rate of fission gases, which is not conducive to the increase in the burnup of fuel elements and affects the safety and economy of nuclear power. [0003] In order to reduce the thermal stress of pellets and reduce the release rate of fission gas, adding second-ph...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/62G21C21/02
CPCG21C3/62G21C21/02Y02E30/30
Inventor 黄华伟严岩刘彤李锐孙茂州马赵丹丹高思宇张显生武海龙
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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