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Rapid preparation method of beryllium oxide-enhanced uranium dioxide nuclear fuel

A technology of uranium dioxide and beryllium oxide, applied in the direction of reactor fuel elements, reactor fuel materials, nuclear engineering, etc., can solve the problems of low thermal conductivity of fuel pellets, achieve low density, reduce sintering temperature, and good compatibility Effect

Active Publication Date: 2017-10-20
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to solve the above-mentioned technical problems, to provide a rapid preparation method of beryllium oxide enhanced uranium dioxide nuclear fuel, the preparation method is fast and efficient, and the prepared beryllium oxide enhanced uranium dioxide nuclear fuel can solve existing UO 2 The problem of low thermal conductivity of fuel pellets

Method used

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Effect test

preparation example

[0019] This embodiment is aimed at the traditional UO 2 To solve the problems of low thermal conductivity and poor heat dissipation performance of fuel pellets, BeO-coated UO was obtained by using SPS low-temperature rapid pre-firing granulation, spheroidization, and coating processes 2 (UO 2 / BeO) core-shell particles, and then the core-shell particles were subjected to SPS rapid sintering to obtain UO 2 / BeO composite nuclear fuel pellets, in improving UO 2 The thermal conductivity of the fuel pellets does not reduce the high-temperature radiation stability of the fuel pellets in the reactor. Its concrete preparation example is as follows:

example 1

[0021] A rapid preparation method of beryllium oxide enhanced uranium dioxide nuclear fuel, comprising the following steps:

[0022] (1) Put the uranium dioxide powder with a particle size of 50nm into the special graphite mold for SPS low-temperature calcining, and then place it in the SPS sintering furnace for low-temperature rapid pre-sintering. After the heating rate is raised to 800°C, the temperature is kept for 1 minute to obtain the calcined uranium dioxide billet;

[0023] Get a density of 6.0g / cm 3 uranium dioxide calcined billets;

[0024] (2) Crushing and sieving the uranium dioxide calcined billet to obtain uranium dioxide particles with a particle size of 15 mesh; uranium dioxide pellets;

[0025] (3) Put the uranium dioxide pellets into the mixing and coating equipment, add beryllium oxide micropowder with a volume ratio of 0.12:1 to the uranium dioxide pellets and a particle size of 5 μm, and mix and coat for 0.5 hours to obtain beryllium oxide Uniform uran...

example 2

[0028] (1) Put the uranium dioxide powder with a particle size of 20nm into the special graphite mold for SPS low-temperature calcining, and then place it in the SPS sintering furnace for low-temperature rapid pre-sintering. After the heating rate is raised to 700°C, keep it warm for 10 minutes to obtain a density of 6.5g / cm 3 uranium dioxide calcined billets;

[0029] (2) Crushing and sieving the uranium dioxide calcined billet to obtain uranium dioxide particles with a particle size of 100 mesh; uranium dioxide pellets;

[0030] (3) Put uranium dioxide pellets into the mixing and coating equipment, add beryllium oxide micropowder with a volume ratio of 0.15:1 to uranium dioxide pellets and a particle size of 20 μm, and mix and coat for 4 hours to obtain beryllium oxide Uniform uranium dioxide / beryllium oxide core-shell structure particles are coated on the surface of uranium dioxide pellets;

[0031] (4) Put uranium dioxide / beryllium oxide core-shell particles into SPS si...

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Abstract

The invention discloses a rapid preparation method of beryllium oxide-enhanced uranium dioxide nuclear fuel. The preparation method comprises preparing BeO-coated UO2(UO2 / BeO) core-shell structure particles through SPS low-temperature rapid pre-sintering granulation, spheroidization and coating processes, and carrying out SPS rapid sintering on the core-shell structure particles to obtain a UO2 / BeO composite nuclear fuel pellet. The preparation method is fast and efficient. The beryllium oxide-enhanced uranium dioxide nuclear fuel can solve the problem that the existing UO2 fuel pellet has low thermal conductivity.

Description

technical field [0001] The invention relates to the field of nuclear fuel, in particular to a rapid preparation method of beryllium oxide enhanced uranium dioxide nuclear fuel. Background technique [0002] Uranium dioxide (UO 2 ) is currently the most widely used nuclear fuel material for fission reactors, and has ideal properties in many nuclear fuel applications, such as small thermal neutron capture cross section, good radiation resistance, good high temperature stability, and good compatibility with cladding materials, etc. . However, UO 2 There is a defect of low thermal conductivity, which is not only an important factor limiting the operating performance of nuclear power plant reactors, but more seriously, it has been found through research that the low thermal conductivity of fuel pellets and poor heat dissipation have become the key to major nuclear accidents one of the factors. [0003] Under normal operating conditions, due to UO 2 The thermal conductivity i...

Claims

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Application Information

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IPC IPC(8): G21C3/62
CPCG21C3/623Y02E30/30
Inventor 杨振亮刘彤李冰清黄华伟高瑞孙茂州贾建平马赵丹丹
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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