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Preparation process of crack-free zirconium alloys

A preparation process and technology of zirconium alloy, applied in the field of preparation technology of crack-free deuterium storage zirconium alloy, can solve the problems of difficult preparation of deuterium (hydrogen) zirconium

Inactive Publication Date: 2013-07-17
UNIV OF SCI & TECH BEIJING
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Literature [4] (S.H.Yun, S.Cho, M.Chang, Estimation of Thermophysical Properties in Massive ZrCoHx System, Fusion Science and Technology, 56(2)(2009)867-872.) and literature [5](N. Bekris, U.Besserer, M.Sirch, R.D.Penzhorn, On the thermal stability of the zirconium / cobalt hydrogen system, Fusion Engineering and Design, 49-50(2000) 781-789.) reported that ZrCo also has pulverization, The volume expansion after storing deuterium can reach about 20%, which causes the cracking of the zirconium alloy, making it difficult to prepare bulk deuterium (hydrogen) zirconium

Method used

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Embodiment 1

[0029] The atomic level pure zirconium will be processed into a small disc with a diameter of 8mm and a thickness of 1mm, smoothed on sandpaper, and cleaned with absolute ethanol. After the sample is placed in the sample chamber, the sample chamber is evacuated to 10 -3 Pa. After the sample chamber is heated to the reaction temperature of 950°C, it is filled with 0.04 atm deuterium gas to carry out the deuterium absorption reaction. After 20 minutes of heat preservation, the temperature was lowered at a rate of 0.5°C / min, and the furnace was cooled to room temperature after falling to a certain temperature of 500°C, and the samples were taken out to obtain a crack-free deuterium storage zirconium alloy with a deuterium storage content of 2.7% (mass%).

Embodiment 2

[0031] Process Zr-2 into a small disc with a diameter of 8 mm and a thickness of 1 mm, smooth it on sandpaper, and clean it with absolute ethanol. After the sample is placed in the sample chamber, the sample chamber is evacuated to 10 -3 Pa. After the sample chamber is heated to a reaction temperature of 900°C, it is filled with 1 atm of deuterium gas to carry out deuterium absorption reaction. After 30 minutes of heat preservation, the temperature was lowered at a rate of 0.5°C / min, and then furnace cooled to room temperature after falling to a certain temperature of 500°C, and the samples were taken out to obtain a crack-free deuterium-storing zirconium alloy with a deuterium storage capacity of 3.5 (mass%).

Embodiment 3

[0033] Process Zr-4 into a small disc with a diameter of 8 mm and a thickness of 1 mm, smooth it on sandpaper, and clean it with absolute ethanol. After the sample is placed in the sample chamber, the sample chamber is evacuated to 10 -3 Pa. After the sample chamber is heated to a reaction temperature of 850°C, it is filled with 2 atm deuterium gas to carry out deuterium absorption reaction. After 40 minutes of heat preservation, the temperature was lowered at a rate of 1°C / min, and the furnace was cooled to room temperature after falling to a certain temperature of 500°C, and the sample was taken out to obtain a crack-free deuterium-storing zirconium alloy with a deuterium storage capacity of 4.0% (mass%). figure 2 A low-magnification schematic diagram of the alloy, image 3 SEM schematic at 500X.

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Abstract

The invention belongs to the field of metallic hydrogen storage materials, and relates to a preparation process of crack-free deuterium storage zirconium alloys. The preparation process is characterized in that the preparation process is implemented by taking an industrial zirconium alloy as a raw material through the steps of carrying out deuterium absorption reaction in a certain temperature and pressure range firstly; then, cooling to a certain temperature at a certain cooling speed, and carrying out furnace cooling so as to obtain crack-free zirconium alloys with a deuterium storage quantity of 2.3-4.0% (mass %). The preparation process disclosed by the invention is simple, low in cost and high in deuterium storage quantity, and has crack-free surfaces. The deuterium storage zirconium alloys prepared by using the process disclosed by the invention have relatively broad prospects in the fields of national defense and nuclear energy engineering such as tracer elements, neutron scattering and nuclear magnetic resonance and the like in the aspects of nuclear fusion reaction, airborne and shipborne laser weapons, light water reactor fuel rods and civil application.

Description

technical field [0001] The invention belongs to the field of metal hydrogen storage materials, and relates to a preparation process of a crack-free deuterium storage zirconium alloy. Background technique [0002] As people's demand for energy increases day by day, nuclear energy has become one of the main ways for countries in the world, especially China, to develop energy. With the frequent occurrence of nuclear power plant accidents, such as the Chernobyl nuclear power plant in the former Soviet Union and the Fukushima nuclear power plant in Japan, nuclear leaks have occurred successively, and people have doubts about the use of nuclear energy. In this context, another form of nuclear energy, nuclear fusion energy, has returned to people's attention. It releases energy through the fusion of deuterium and tritium atoms, not only the energy released is huge, far greater than the energy produced by nuclear fission, but also, due to the harsh reaction conditions, it can autom...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C16/00C22C1/00
Inventor 宋西平窦娜娜杨云马明旺向伟
Owner UNIV OF SCI & TECH BEIJING
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