Preparation method and application of uranium-based ternary carbide

A ternary carbide and carbide technology, applied in the direction of reactor fuel material, nuclear power generation, climate sustainability, etc., can solve the problems affecting the stability of UC pellets, insufficient oxidation resistance, and swelling of uranium carbide irradiation, etc. Achieve the effect of improving antioxidant performance, enhancing lattice stability, and reducing reaction

Active Publication Date: 2017-08-04
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

However, the radiation swelling of uranium carbide is serious, the anti-oxidation performance is insufficient, the reactivity with water is high, and the complex preparation process limits its practical appl

Method used

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Examples

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Effect test

preparation example Construction

[0023] A method for preparing uranium-based ternary carbides is prepared by reaction sintering of uranium compounds and transition metal carbides. Specifically include the following steps:

[0024] Step A, preparation of raw materials: the sum of the total mass percentages of the raw materials is calculated as 100%, including the following components: 10-89.9wt.% uranide powder, 10-89.9wt.% transition metal carbide powder, 0-11.4% carbon powder, and lubricant 0.1wt.% Ake wax,

[0025] Put the above components in a nylon ball mill jar, based on the total mass of the above components, add 1-2 times the total mass of alcohol and 3 times the total mass of zirconia grinding balls, and wet mix the balls for 24 hours, Afterwards, dry at 70-100°C for 24 hours and sieve to obtain the raw material;

[0026] Step B, placing the raw material obtained in step A in a designed sintering mold for reaction sintering to obtain a highly stable uranium-based ternary carbide.

[0027] In the ab...

Embodiment 1

[0035] Step A, proportioning raw materials as follows:

[0036] Uranium carbide, 5 μm, 235U enrichment 2%, 10wt.%; ZrC, 40 μm, 89.9wt.%; Acrawax, 0.1wt.%. Put the above powder in a nylon ball mill jar, add 1 times the mass of alcohol and 3 times the mass of zirconia grinding balls, wet mix and grind the balls for 24 hours, then dry at 70°C for 24 hours and sieve.

[0037] Step B, carry out sintering as follows:

[0038] The mixed powder is placed in a hot pressing sintering mold for reaction sintering. First evacuate to 5×10 -2 Pa, raised to 600°C at a rate of 20°C / min and held for 0.5h for degreasing; then filled with argon to 10kPa, raised to 1900°C at a rate of 5°C / min and held for 4h, while applying a sintering pressure of 100MPa, holding After the pressure holding is completed, the furnace is cooled.

[0039] Step C, take out the sample after cooling with the furnace, and process it to the required shape and size.

Embodiment 2

[0041] Step A, proportioning raw materials as follows:

[0042] Uranium carbide, 40μm, 235 U enrichment 20%, 89.9wt.%; NbC, 5μm, 10wt.%; Acrawax, 0.1wt.%. Put the above powder in a nylon ball mill jar, add 2 times the mass of alcohol and 3 times the mass of zirconia grinding balls, wet mix and grind the balls for 24 hours, then dry at 100°C for 24 hours and sieve.

[0043] Step B, carry out sintering as follows:

[0044] The mixed powder is placed in a hot pressing sintering mold for reaction sintering. First evacuate to 5×10 -1 Pa, raised to 600°C at a rate of 5°C / min and held for 2 hours for degreasing; then filled with argon to 50kPa, raised to 2100°C at a rate of 10°C / min and held for 1 hour, and a sintering pressure of 20MPa was applied at the same time. After pressing, the furnace is cooled.

[0045] Step C, take out the sample after cooling with the furnace, and process it to the required shape and size.

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Abstract

The invention discloses a preparation method and application of uranium-based ternary carbide, and is used for overcoming the shortcomings of the uranium monocarbidc (UC) and uranium dioxide (UO2) nuclear fuels in the prior art on the aspects of melting point, heat conduction, irradiance resistance, and the like. The preparation method comprises the steps of processing mixing uranium carbide powder and transition metal carbide powder or mixing uranium dioxide powder and transition metal carbide powder and carbon powder, placing in a designed graphite jig, and allowing reactive sintering to obtain high-stability uranium-based ternary carbide. The uranium-based ternary carbide prepared by the preparation method of the invention has the characteristics of high melting point, high heat conductivity and good irradiation resistance, and can be used as an accident fault-tolerance nuclear fuel of a nuclear power station, or a nuclear fuel of a nuclear-powered rocket.

Description

technical field [0001] The invention relates to a preparation method and application of uranium-based ternary carbide. Background technique [0002] Japan's Fukushima "311" nuclear accident exposed traditional UO 2 The major hidden dangers of the +Zr alloy fuel system under accident conditions have triggered worldwide discussions on accident-tolerant fuels. Accident-tolerant fuel is a new-generation fuel concept proposed to improve the performance of fuel elements against severe accidents, specifically refers to: the same as the current UO 2 Fuel systems that can resist loss of coolant accidents for a longer period of time than +Zr fuels, while maintaining or improving their performance under normal operating conditions. The development of alternative materials for Zr alloys and the development of fuel pellets with high thermal conductivity and excellent safety performance are one of the main directions for the development of accident-tolerant fuels. [0003] UC and UO 2...

Claims

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Application Information

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IPC IPC(8): C04B35/56C04B35/645G21C3/58
CPCC04B35/56C04B35/645C04B2235/32C04B2235/422C04B2235/6562G21C3/58Y02E30/30
Inventor 李冰清杨振亮高瑞贾建平唐浩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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