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Zirconium alloy having excellent corrosion resistance and creep resistance and method of manufacturing the same

a zirconium alloy and creep resistance technology, applied in the field of zirconium alloys, can solve the problems of mechanical properties of conventional zirconium alloys, corrosion and creep properties in severe operating conditions may deteriorate, and achieve the effects of maximizing corrosion resistance and creep resistance, and increasing corrosion resistan

Inactive Publication Date: 2016-10-20
KEPCO NUCLEAR FUEL CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Benefits of technology

The present invention provides a zirconium alloy composition and final annealing conditions that optimize corrosion resistance and creep resistance. The alloy composition includes the removal of saponin (Sn) and the addition of niobium (Nb), phosphorus (P), tantalum (Ta) and other elements. The final annealing conditions include a specific temperature range and duration. The resulting zirconium alloy exhibits superior corrosion resistance and creep resistance compared to existing alloys, making it ideal for use in nuclear fuel cladding tubes and other applications.

Problems solved by technology

Mechanical properties of conventional zircaloy, such as corrosion and creep properties in severe operating conditions may deteriorate.

Method used

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  • Zirconium alloy having excellent corrosion resistance and creep resistance and method of manufacturing the same
  • Zirconium alloy having excellent corrosion resistance and creep resistance and method of manufacturing the same

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Preparation of Zirconium Alloys

[0043](1) Formation of Ingot

[0044]In step (1), 1.2 wt % of Nb, 0.02 to 0.05 wt % of P, 0.03 to 0.1 wt % of Ta, 0.2 wt % of Fe, and the balance of Zr were subjected to VAR (Vacuum Arc Remelting), thus forming an ingot.

[0045]The Zr that was used is zirconium sponge (Reactor Grade ASTM B349), and the added elements, such as Nb, P, Ta, Fe and the like, have a high purity of 99.99% or more.

[0046]In order to prevent the segregation of impurities and the non-uniform distribution of the alloy composition, this process was repeated about three times, and the alloy was melted under the condition that the chamber for VAR was maintained at a vacuum level of 10−5 torr or less, thus forming an ingot. Unlike the other alloy elements, P was melted after being compacted, in order to prevent precipitation and segregation.

[0047]To prevent the surface of the sample from being oxidized during the cooling, cooling was carried out inert gas environment such as argon.

[0048](2...

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Abstract

A zirconium alloy is manufactured through melting; solution heat treatment at 1,000 to 1,050° C. for 30 to 40 min and β-quenching using water; preheating at 630 to 650° C. for 20 to 30 min and hot rolling at a reduction ratio of 60 to 65%; primary intermediate vacuum annealing at 570 to 590° C. for 3 to 4 hr and primarily cold-rolled at a reduction ratio of 30 to 40%; secondary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and secondarily cold-rolled at a reduction ratio of 50 to 60%; tertiary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and tertiarily cold-rolled at a reduction ratio of 30 to 40%; and final vacuum annealing at 440 to 650° C. for 7 to 9 hr.

Description

BACKGROUND OF THE INVENTION[0001]1. Field of the Invention[0002]The present invention relates to a zirconium alloy having excellent corrosion resistance and creep resistance and a method of manufacturing the same and, more particularly, to a zirconium alloy composition and annealing conditions, suitable for use in nuclear fuel cladding tubes and spacer grids for light and heavy water reactor nuclear power plants.[0003]2. Description of the Related Art[0004]Zirconium alloys, having a low neutron absorption cross-section, superior corrosion resistance and mechanical properties, have been widely used for decades as materials for nuclear fuel cladding tubes, nuclear fuel assembly spaer grids, and internal structures in nuclear reactors.[0005]Among the alloys, Zircaloy-2 (Sn: 1.20 to 1.70 wt %, Fe: 0.07 to 0.20 wt %, Cr: 0.05 to 1.15 wt %, Ni: 0.03 to 0.08 wt %, O: 900 to 1500 ppm, Zr: balance) and Zircaloy-4 (Sn: 1.20 to 1.70 wt %, Fe: 0.18 to 0.24 wt %, Cr: 0.07 to 1.13 wt %, O: 900 to...

Claims

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Application Information

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Patent Type & Authority Applications(United States)
IPC IPC(8): C22C16/00C22F1/18B22D7/00C22C1/02
CPCC22C16/00B22D7/005C22F1/186C22C1/02B22F1/00
Inventor CHOI, MIN YOUNGMOK, YONG KYOONKIM, YOON HONA, YEON SOOLEE, CHUNG YONGJUNG, TAE SIKGO, DAE GYUNLEE, SEUNG JAEKIM, JAE IK
Owner KEPCO NUCLEAR FUEL CO LTD
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