Zirconium based alloys having excellent creep resistance

A technology of zirconium-based alloys and zirconium alloys, applied in the field of zirconium-based alloy composite materials

Active Publication Date: 2006-08-16
KEPCO NUCLEAR FUEL CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, nuclear power plants are currently operating under severe conditions to provide economics, so nuclear-coated tubes made with conventional alloys such as zirconium alloy-4 have reached the limits of their use

Method used

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  • Zirconium based alloys having excellent creep resistance
  • Zirconium based alloys having excellent creep resistance

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1～13

[0053] Embodiment 1~13: the preparation method of zirconium alloy

[0054] Examples of 4 alloys with a niobium content of 0.8% to 1.8%:

[0055] (1) Zr-0.8%Nb-0.07%Cu-0.14%O-0.008%C-0.008%Si-0.002%S;

[0056] (2) Zr-1.1%Nb-0.07%Cu-0.14%O-0.008%C-0.008%Si-0.002%S;

[0057] (3) Zr-1.5%Nb-0.07%Cu-0.14%O-0.008%C-0.008%Si-0.002%S; and

[0058] (4) Alloy of Zr-1.8%Nb-0.07%Cu-0.14%O-0.008%C-0.008%Si-0.002%SZr-1.5%Nb-0.4%Sn:

[0059] (5) Zr-1.5%Nb-0.4%Sn-0.14%O-0.008%C-0.008%Si-0.002%S

[0060] Four alloy examples prepared by adding one or more elements selected from Cu, Fe and Cr to the above alloy comprising Zr-1.5%Nb-0.4%Sn:

[0061] (6) Zr-1.5%Nb-0.4%Sn-0.1%Cu-0.14%O-0.008%C-0.008%Si-0.002%S;

[0062] (7) Zr-1.5%Nb-0.4%Sn-0.1%Fe-0.14%O-0.008%C-0.008%Si-0.002%S;

[0063] (8) Zr-1.5%Nb-0.4%Sn-0.1%Cu-0.1%Fe-0.14%O-0.008%C-0.008%Si-0.002%S;

[0064] and

[0065] (9) Zr-1.5%Nb-0.4%Sn-0.2%Fe-0.1%Cr-0.14%O-0.008%C-0.008%Si-0.002%S

[0066] Examples of 4 alloys with an S conten...

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PUM

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Abstract

The present invention relates to a zirconium-based alloy composite material with excellent creep resistance, more specifically, to a zirconium-based alloy that undergoes a final heat treatment to improve the creep resistance so that the degree of recrystallization is 40-70% composite material. The zirconium-based alloy comprises 0.8 to 1.8% by weight of niobium (Nb); 0.38 to 0.50% by weight of tin (Sn); selected from 0.1 to 0.2% by weight of iron (Fe), 0.05 to 0.15% by weight of copper (Cu) and 0.12% by weight of one or more elements in chromium (Cr); 0.10-0.15% by weight of oxygen (O); 0.006-0.010% by weight of carbon (C); 0.006-0.010% by weight of silicon (Si); 0.0005-0.0020% by weight of sulfur (S); and the balance of zirconium (Zr). The zirconium alloy prepared with the composition according to the present invention has excellent creep resistance compared with conventional zirconium alloy-4, and can be effectively used as nuclear coating tubes, support grids in nuclear power plants utilizing light water or heavy water reactors and the internal structure of the reactor core.

Description

technical field [0001] The present invention relates to a zirconium-based alloy composite material with excellent creep resistance, more specifically, to a zirconium-based alloy that undergoes a final heat treatment to improve the creep resistance so that the degree of recrystallization is 40-70% composite material. The zirconium-based alloy composite material comprises 0.8 to 1.8% by weight of niobium (Nb); 0.38 to 0.50% by weight of tin (Sn); selected from 0.1 to 0.2% by weight of iron (Fe), 0.05 to 0.15% by weight of copper (Cu ) and 0.12% by weight of one or more elements in chromium (Cr); 0.10 to 0.15% by weight of oxygen (O); 0.006 to 0.010% by weight of carbon (C); 0.006 to 0.010% by weight of silicon (Si ); 0.0005-0.0020% by weight of sulfur (S); and the balance of zirconium (Zr). Background technique [0002] Nuclear fuel coated tubes used in nuclear power plants are one of the important components used in nuclear reactor cores. The coated tube confines the nucle...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C16/00
CPCC22C16/00C22F1/186
Inventor 郑龙焕白种爀崔秉权朴相允李明镐方济健朴正容金埈焕金铉佶郑然浩
Owner KEPCO NUCLEAR FUEL CO LTD
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