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A kind of preparation method of Fecral-based ODS alloy for nuclear reactor core

A nuclear reactor and alloy technology, applied in metal processing equipment, transportation and packaging, etc., can solve the problems of poor corrosion resistance, deterioration of material mechanical properties, etc., and achieve high mechanical strength, good high-temperature mechanical strength and high-temperature oxidation and corrosion resistance. performance effect

Active Publication Date: 2021-08-31
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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  • A kind of preparation method of Fecral-based ODS alloy for nuclear reactor core
  • A kind of preparation method of Fecral-based ODS alloy for nuclear reactor core

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

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

[0029] Step 1, based ODS FeCrAl alloy composition according to the formula Fe, Cr, W, Al, Ti, Nb, V melting elements, pure iron with a purity of greater than 99.9% and a high purity alloy ingredient formulation according to Table 1 by vacuum induction smelting furnace; melting alloy after milling atomization technology obtained from 50 mesh to mesh alloy powder, the alloy powder atomized oxygen control object 200 0.05wt% or less.

[0030] Step 2, the alloy powder Zr and Y 2 O 3 Ball milling the powder to mechanical alloying treatment; DETAILED dry milling method is ball milling, the milling time was 30h, the ball feed ratio of 10: 1, the size of the powder obtained after milling is 65μm ~ 130μm.

[0031] Step 3, the milled powder enclosed in a steel sheath sintering densification by hot isostatic pressing; hot isostatic pressure treatment 150MP...

Embodiment 2

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

[0037] Step 1, based ODS FeCrAl alloy composition according to the formula Fe, Cr, W, Al, Ti, Nb, V melting elements, pure iron with a purity of greater than 99.9% and a high purity alloy ingredient formulation according to Table 1 by vacuum induction smelting furnace; melting alloy after milling atomization technology obtained from 50 mesh to mesh alloy powder, the alloy powder atomized oxygen control object 200 0.05wt% or less.

[0038] Step 2, the alloy powder Zr and Y 2 O 3 Ball milling the powder to mechanical alloying treatment; DETAILED dry milling method is ball milling, the milling time was 30h, the ball feed ratio of 10: 1, the size of the powder obtained after milling is 65μm ~ 130μm.

[0039] Step 3, the milled powder enclosed in a steel sheath sintering densification by hot isostatic pressing; hot isostatic pressure treatment 150MP...

Embodiment 3

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

[0045] Step 1, based ODS FeCrAl alloy composition according to the formula Fe, Cr, W, Al, Ti, Nb, V melting elements, pure iron with a purity of greater than 99.9% and a high purity alloy ingredient formulation according to Table 1 by vacuum induction smelting furnace; melting alloy after milling atomization technology obtained from 50 mesh to mesh alloy powder, the alloy powder atomized oxygen control object 200 0.05wt% or less.

[0046] Step 2, the alloy powder Zr and Y 2 O 3 Ball milling the powder to mechanical alloying treatment; DETAILED dry milling method is ball milling, the milling time was 30h, the ball feed ratio of 10: 1, the size of the powder obtained after milling is 65μm ~ 130μm.

[0047] Step 3, after the powder is enclosed in a steel ball mill sheath by hot isostatic densification sintering; hot isostatic pressing, the first h...

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Abstract

The invention discloses a preparation method of FeCrAl-based ODS alloy for nuclear reactor core. According to the composition formula of FeCrAl-based ODS alloy, Fe, 7-10% Cr, 1.0-2.5% W, 3.5-5.5% Al, 0-1.2% Nb, 0-0.5% Ti, 0-0.3% V elements are smelted to obtain an alloy, and the smelted alloy is prepared into an alloy powder; the alloy powder is mixed with 0.4-1.0% Zr and 0.25-0.5% Y 2 o 3 The powder is subjected to mechanical alloying and ball milling; the powder after ball milling is sintered and densified by hot isostatic pressing; the alloy blank is obtained after hot isostatic pressing and subjected to forging treatment; the forged sample is subjected to hot rolling treatment to obtain FeCrAl-based ODS alloy. The FeCrAl-collected ODS alloy obtained by optimizing the components and controlling the process of the invention has good mechanical properties at room temperature and high temperature, and excellent high-temperature oxidation resistance and corrosion resistance.

Description

Technical field [0001] The present invention relates to nuclear reactor shell material package technical field, particularly relates to a method for producing a nuclear reactor core based ODS FeCrAl alloy. Background technique [0002] The fuel element is a core member of the nuclear reactor core, its performance is directly related to the safety and economy of nuclear reactor operation. Zirconium alloys are commercial nuclear power LWR fuel element cladding material only use. However, in emergency situations (e.g., Japanese Fukushima PWR loss of coolant accident, etc.), alloy cladding reacts violently with high temperature coolant water, emit a lot of heat and explosive hydrogen gas, resulting in deterioration of the mechanical properties of the cladding material generating a large number of reactors with the explosion of hydrogen leakage and other nuclear radioactive products disastrous consequences. Therefore, the next generation and advanced pressurized water reactor nuclear ...

Claims

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Application Information

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Patent Type & Authority Patents(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