Zirconium base alloy used for light-water reactors and preparation method thereof

A zirconium-based alloy and reactor technology, applied in the field of zirconium alloy materials, can solve the problems of decreased corrosion resistance, uneven growth, and inability to disperse and distribute, and achieve the effects of improving corrosion resistance and mechanical properties.

Active Publication Date: 2015-07-01
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0015] However, the cooling rate of the core of the large-sized ingot is insufficient after the β-phase quenching process, and precipitates are inevitably generated at the α-phase boundary. The precipitates in the existing zirconium alloy processing technology are distributed in bands, and in the The α-phase hot rolling/hot extrusion process grows unevenly during the heat preservation process, so that the second phase particles in the zirconium alloy cannot be dispersed, resulting in poor plastic defor

Method used

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  • Zirconium base alloy used for light-water reactors and preparation method thereof
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  • Zirconium base alloy used for light-water reactors and preparation method thereof

Examples

Experimental program
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Effect test

Embodiment 1

[0149] The first step, preparation of alloy ingot

[0150] The use of nuclear-grade sponge zirconium and nuclear-grade pure metal raw materials (Nb, Sn, Fe, Cu, Si) or master alloys is based on 0.35% by weight of niobium, 0.65% by weight of tin, 0.3% by weight of iron, and 0.05% by weight of Copper, 0.13% by weight of oxygen, 0.008% by weight of silicon and the balance of at least 98% by weight of zirconium containing impurities are smelted multiple times in a vacuum consumable electric arc furnace to produce an alloy ingot.

[0151] The second step, forging and β water quenching

[0152] The above alloy ingot is forged at 1000°C, processed into a billet, scaled, pickled to remove grease, and then subjected to β-phase homogenization treatment at 1050°C for 30 minutes and then water quenched. The quenching speed is greater than 30°C / s.

[0153] The third step, hot rolling treatment

[0154] After heating at 650°C for 50 minutes, hot rolling is carried out 5 to 6 times. During...

Embodiment 2

[0158] Implement this embodiment with the same zirconium alloy composition ratio as in Example 1, the difference is that the preparation method of the zirconium-based alloy is different, specifically as follows:

[0159] The first step is to prepare zirconium-based alloy ingots

[0160] Using nuclear-grade sponge zirconium and nuclear-grade pure metal raw materials (Nb, Sn, Fe, Cu, Si) or intermediate alloys according to the alloy composition of Example 1, respectively, using a vacuum consumable electric arc furnace for multiple melting, it is made alloy ingot.

[0161] The second step, forging and β water quenching

[0162] The alloy ingot is forged at 950-1050°C, processed into an alloy billet, after removing scale and pickling to remove grease, after 10-60 minutes of β-phase homogenization treatment at 1000-1100°C, water quenching, the quenching speed is greater than 30 °C / s.

[0163] The third step, hot rolling treatment

[0164] The alloy billet is heated at 580-700°C...

Embodiment 3

[0175] This example was carried out in the same preparation method as in Example 2, except that, in the components of the zirconium-based alloy, 0.44% by weight of niobium, 0.45% by weight of tin, 0.3% by weight of iron, 0.01% by weight of % copper, 0.13% by weight oxygen, 0.008% by weight silicon and the balance being a component batch of at least 98% by weight zirconium containing impurities.

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Abstract

The invention discloses a zirconium base alloy used for light-water reactors. The zirconium base alloy contains, by weight, 0.30-0.69% of tin, 0.20-0.50% of niobium, 0.20-0.40% of iron, 0.01-0.09% of copper, 0.07-0.20% of oxygen, 0.005-0.03% of silicon and the balance zirconium. According to the invention, the minimum total percentage of the added copper, the silicon and the oxygen is limited to 0.13%, and the matching performance among the copper, the silicon and the oxygen is considered, so that the corrosion resistance of the zirconium base alloy is improved; meanwhile, the mechanical property, the radiation growth resistance and the radiation creeping resistance of the alloy can be improved.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a zirconium-based alloy used in light water reactors and a preparation method thereof. Background technique [0002] Zirconium-based alloys are widely used as cladding materials and core structure materials for water-cooled power reactors due to their small thermal neutron absorption cross-section, good corrosion resistance and good mechanical strength in high-temperature water and high-temperature steam. With the development of nuclear power reactor technology in the direction of increasing fuel burnup, reducing fuel cycle costs, increasing reactor thermal efficiency, and improving safety and reliability, the corrosion resistance and creep resistance of zirconium-based alloys for key core component fuel element cladding materials Performance, hydrogen absorption performance, mechanical properties and radiation dimensional stability put forward higher requirements. [00...

Claims

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Application Information

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IPC IPC(8): C22C16/00C22F1/18C22F1/02G21C3/07
CPCY02E30/30
Inventor 曾奇锋黄锦华陈磊刘家正卢俊强朱丽兵
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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