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Preparation method of FeCrAl based ODS alloy used for nuclear reactor cores

A nuclear reactor and alloy technology, applied in metal processing equipment, transportation and packaging, etc., can solve problems such as poor corrosion resistance and deterioration of material mechanical properties, achieve high mechanical strength, improve room temperature mechanical properties of alloys and high temperature strength, good high temperature The effect of mechanical strength and high temperature oxidation and corrosion resistance

Active Publication Date: 2020-02-25
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

For ferritic ODS steel, a major problem restricting its development is relatively poor corrosion resistance
The usual method is to increase the Cr content to improve its oxidation resistance. Increasing the Cr content can improve the oxidation resistance. However, the material has an enriched area of ​​Cr in the long-term service environment, which seriously deteriorates the mechanical properties of the material.

Method used

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  • Preparation method of FeCrAl based ODS alloy used for nuclear reactor cores
  • Preparation method of FeCrAl based ODS alloy used for nuclear reactor cores

Examples

Experimental program
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Effect test

Embodiment 1

[0028] This embodiment provides a method for preparing a FeCrAl-based ODS alloy for a nuclear reactor core, and the specific steps are as follows:

[0029] Step 1: Smelt Fe, Cr, W, Al, Ti, Nb, and V elements according to the composition formula of FeCrAl-based ODS alloy, use industrial pure iron and high-purity alloys with a purity greater than 99.9% according to the formula in Table 1, and use vacuum induction The smelting furnace is used for smelting; the smelted alloy is atomized and powdered to obtain alloy powder with a mesh number of 50 mesh to 200 mesh, and the oxygen content of the atomized alloy powder is controlled below 0.05wt.%.

[0030] Step 2, alloy powder with Zr and Y 2 o 3 The powder is subjected to mechanical alloying ball milling; the specific ball milling method is dry milling, the ball milling time is 30 hours, the ball-to-material ratio is 10:1, and the size of the powder obtained after ball milling is 65 μm to 130 μm.

[0031] Step 3, the ball-milled p...

Embodiment 2

[0036] This embodiment provides a method for preparing a FeCrAl-based ODS alloy for a nuclear reactor core, and the specific steps are as follows:

[0037] Step 1: Smelt Fe, Cr, W, Al, Ti, Nb, and V elements according to the composition formula of FeCrAl-based ODS alloy, use industrial pure iron and high-purity alloys with a purity greater than 99.9% according to the formula in Table 1, and use vacuum induction The smelting furnace is used for smelting; the smelted alloy is atomized and powdered to obtain alloy powder with a mesh number of 50 mesh to 200 mesh, and the oxygen content of the atomized alloy powder is controlled below 0.05wt.%.

[0038] Step 2, alloy powder with Zr and Y 2 o 3 The powder is subjected to mechanical alloying ball milling; the specific ball milling method is dry milling, the ball milling time is 30 hours, the ball-to-material ratio is 10:1, and the size of the powder obtained after ball milling is 65 μm to 130 μm.

[0039] Step 3, the ball-milled p...

Embodiment 3

[0044] This embodiment provides a method for preparing a FeCrAl-based ODS alloy for a nuclear reactor core, and the specific steps are as follows:

[0045] Step 1: Smelt Fe, Cr, W, Al, Ti, Nb, and V elements according to the composition formula of FeCrAl-based ODS alloy, use industrial pure iron and high-purity alloys with a purity greater than 99.9% according to the formula in Table 1, and use vacuum induction The smelting furnace is used for smelting; the smelted alloy is atomized and powdered to obtain alloy powder with a mesh number of 50 mesh to 200 mesh, and the oxygen content of the atomized alloy powder is controlled below 0.05wt.%.

[0046] Step 2, alloy powder with Zr and Y 2 o 3 The powder is subjected to mechanical alloying ball milling; the specific ball milling method is dry milling, the ball milling time is 30 hours, the ball-to-material ratio is 10:1, and the size of the powder obtained after ball milling is 65 μm to 130 μm.

[0047] Step 3, the ball-milled p...

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Abstract

The invention discloses a preparation method of a FeCrAl based ODS alloy used for nuclear reactor cores. An alloy is obtained by conducting smelting on elements including 7%-10% of Fe, 1.0-2.5% of Cr,3.5-5.5% of Al, 0%-1.2% of Nb, 0%-0.5% of Ti and 0%-0.3% of V according to the component formula of the FeCrAl based ODS alloy, and alloy powder is made of the alloy obtained after smelting; mechanical alloying ball milling processing is conducted on the alloy powder, 0.4%-1.0% of Zr powder and 0.25%-0.5% of Y2O3 powder; sintering densification is conducted on the powder, obtained after ball milling, through hot isostatic pressing; forging processing is conducted on an alloy blank obtained after hot isostatic pressing; and the FeCrAl based ODS alloy is obtained by conducting hot rolling processing on a sample obtained after forging. The FeCrAl based ODS alloy obtained by optimizing components and the control process has good normal-temperature and high-temperature mechanical properties and excellent high-temperature oxidation resistance and corrosion resistance.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor cladding materials, in particular to a method for preparing a FeCrAl-based ODS alloy for nuclear reactor cores. Background technique [0002] The fuel element is the core component of the nuclear power reactor core, and its performance is directly related to the safety and economy of the nuclear reactor operation. Zirconium alloy is currently the only cladding material used in commercial nuclear power light water reactor fuel elements. However, in emergencies (such as the Fukushima nuclear accident in Japan, the pressurized water reactor loss of water accident, etc.), the zirconium alloy cladding reacts violently with high-temperature coolant water, releasing a large amount of heat and explosive gas hydrogen, resulting in deterioration of the mechanical properties of the cladding material , resulting in nuclear catastrophic consequences such as reactor hydrogen explosion and leakage of a ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C38/28C22C38/26C22C38/24C22C38/22C22C38/06C22C33/02B22F9/08B22F9/04B22F3/15B22F3/17B22F3/18B22F1/00
CPCC22C38/28C22C38/26C22C38/24C22C38/22C22C38/06C22C38/005C22C38/002C22C38/001C22C33/0285B22F9/08B22F9/04B22F3/15B22F3/17B22F3/18B22F2009/043B22F1/05
Inventor 张瑞谦孙永铎郑继云孙超辛勇吴裕龙绍军
Owner NUCLEAR POWER INSTITUTE OF CHINA