Zirconium-base alloy used for light-water reactor

A zirconium-based alloy and reactor technology, which is applied in the field of zirconium alloy materials, can solve problems such as the alloy’s anti-buncle corrosion behavior, and achieve improved uniform corrosion resistance, high creep and fatigue resistance, excellent resistance to uniformity and corrosion resistance. Effect of furuncle corrosion properties

Active Publication Date: 2008-09-17
NUCLEAR POWER INSTITUTE OF CHINA
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  • Description
  • Claims
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Problems solved by technology

Although people can accept the following point of view: the materials that pass the test in 360 °C aqueous solution and 400 °C steam can be used in pressurized water reactors, and those that pass the test in 360 °C lithium-containing aqueous solution are more suitable for use in pressurized water reactors with high lithium concentrations In working conditions, those that pass the test in steam above 500°C can be used in boiling water reactors; moreov

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  • Zirconium-base alloy used for light-water reactor
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  • Zirconium-base alloy used for light-water reactor

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Embodiment Construction

[0024] Hereinafter, the present invention will be described in more detail through specific embodiments.

[0025]Table 1 is the composition of the alloy provided by the present invention, in Table 13 * The Zr-4 alloy composition and the corresponding test results, each content in Table 1 is the weight percentage of the corresponding component in the alloy.

[0026] Table 1 Alloy composition provided by the present invention

[0027] Alloy

Serial number

Sn

Nb

Fe

Cr

O

C

N

Zr and

Impurities

1

0.92

1.02

0.12

---

0.15

0.012

0.008

Margin

2

0.81

1.20

0.44

---

0.10

0.014

0.007

Margin

3

0.96

1.02

0.39

---

0.08

0.013

0.005

Margin

4

0.89

1.25

0.27

---

0.06

0.012

0.010

Margin

...

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Abstract

The invention relates to a zirconium alloy material, particularly to a zirconium-base alloy used for a light water reactor. The zirconium-base alloy is composed of (wt %) Sn 0.80-1.20, Nb 0.90-1.25, Fe 0.12-0.45, O 0.06-0.15, C less than 0.15, N less than 0.008, and zirconium and impurities in balance. By adding Fe and O two elements based on the current Zr-Sn-Nb alloy, the zirconium-base alloy with good corrosion-resisting property in all corrosion tests using 360 DEG C deionized water, 360 DEG C lithium-containing water solution, 400 DEG C steam and 500 DEG C can be prepared. The inventive zirconium-base alloy can be used as structural material of a nuclear reactor core.

Description

Technical field [0001] The invention relates to a zirconium alloy material, in particular to a zirconium-based alloy used in a light water reactor. Background technique [0002] In the development process of light water reactors, including boiling water reactors and pressurized water reactors, fuel design has put forward high requirements on the structural components of the reactor core, such as fuel element cladding, grids, and guide tubes. Currently, these parts are usually made of Zr-2 and Zr-4 alloys. The design of high fuel consumption requires extending the residence time of these components in the stack and increasing the temperature of the coolant, which makes the zirconium alloy components face a more severe corrosion and hydrogen absorption environment. These high requirements have promoted the research to improve the corrosion resistance of Zr-2 and Zr-4 alloys, and promoted the development of new zirconium alloys with better corrosion resistance and hydrogen absorptio...

Claims

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Application Information

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IPC IPC(8): C22C16/00
Inventor 赵文金周邦新苗志蒋有荣彭倩刘彦章苟渊王晓敏易伟吕华权
Owner NUCLEAR POWER INSTITUTE OF CHINA
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