Zirconium alloy powder and preparing method thereof

A zirconium alloy and powder technology, which is applied in the field of nuclear power plant pressurized water reactor fuel assembly manufacturing, can solve the problem of failure to consider the hydrogen content, cladding and related parts quality not up to the requirements, zirconium alloy powder particles cannot meet the requirements of nuclear purity grade, etc. problem, achieve the effect of improving fluidity and reducing hydrogen content

Inactive Publication Date: 2019-11-26
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] In summary, because the existing technology does not consider controlling the hydrogen content in the powder during the preparation of zirconium alloy powder, the obtained zirconium alloy powder particles cannot meet the requirements of nuclear purity grade, which leads to the failure of cladding and related parts manufactured by 3D printing. The quality does not meet the requirements

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  • Zirconium alloy powder and preparing method thereof

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0042] Such as figure 1 Shown a kind of zirconium alloy powder and preparation method thereof, comprises the following steps:

[0043] (A) Furnace loading, sending the zirconium alloy rod into the atomization furnace, vacuumizing and replacing the inert gas in the atomization furnace;

[0044] (B) smelting and atomizing powder making, heating the zirconium alloy rod until the bottom end of the zirconium alloy rod is melted to form molten droplets, and using inert atomizing gas to crush the molten droplets to form zirconium alloy powder;

[0045] (C) sieving, sieving under a protective atmosphere to obtain zirconium alloy powder with particle size meeting the requirements;

[0046] (D) vacuum heat treatment, sieving the zirconium alloy powder obtained in the heat treatment step (E) in a vacuum heat treatment furnace to obtain a zirconium alloy powder with a hydrogen content lower than 25 μg / g;

[0047] (E) out of the oven packaging;

[0048] In the step (C), the protective a...

Embodiment 2

[0053] On the basis of Example 1, in the step (B), the inert atomizing gas is argon, and the atomization process parameters are: the atomization nozzle pressure is 1.1-1.6 MPa, and the bar feed rate is 12-1.6 MPa. 15cm / min;

[0054] The step (B) includes a preheating stage and a smelting stage. After the preheating stage is completed, adjust the atomizing nozzle pressure to 1.1-1.6 MPa, continue to heat up to the smelting stage, and adjust the atomizing nozzle pressure to 1.4-1.6 MPa after entering the smelting stage , control the bar feeding rate to 12-15cm / min, when the atomizing gas pressure is lower than 1.4MPa, stop atomizing;

[0055] In the preheating stage, the preheating current of the induction coil is 50-60A, and in the melting stage, the melting current of the induction coil is 85-100A.

[0056] The two-stage heating can effectively ensure the continuous and stable zirconium alloy liquid flow. At the same time, according to the different heating temperature sectio...

Embodiment 3

[0058] On the basis of the above examples, in the step (A), after the atomization furnace is evacuated, flush the furnace body with an inert gas for 2 to 3 times, and then fill the furnace body with argon to 80-90kPa; the step ( In A), the surface of the zirconium alloy rod is treated before loading into the furnace; the diameter of the zirconium alloy rod is 10-60 mm.

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Abstract

The invention discloses a preparing method of zirconium alloy powder. The method comprises the following steps of A, furnace charging, wherein vacuumizing is carried out in an atomization furnace, andinert gases are replaced; B, smelting and atomizing for powder making, wherein a zirconium alloy bar is heated until the bottom end of the zirconium alloy bar is molten to form molten dripping, and inert atomized gas is used for crushing the molten dripping to form the zirconium alloy powder; C, screening, wherein, under the protective atmosphere, screening is carried out to obtain the zirconiumalloy powder with the granularity meeting the meets; D, vacuum heat treatment, wherein in a vacuum heat treatment furnace, heat treatment is carried out on the zirconium alloy powder obtained throughscreening in the step C, and the zirconium alloy powder with the content of hydrogen lower than 25 micrograms / g; and E, discharge packaging. After screening, the vacuum heat treatment step is introduced for treating the zirconium alloy powder, the hydrogen content of the zirconium alloy powder can be obviously reduced, the nuclear-pure-level component needs are met, the fluidity of the zirconium alloy powder can be obviously improved, and the made zirconium alloy powder can be directly applied to 3D printing process making of nuclear power station fuel assembly related parts like cladding.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant pressurized water reactor fuel assembly manufacturing, in particular to a zirconium alloy powder and a preparation method thereof. Background technique [0002] The wide application of metal powder has promoted the rapid development of powder preparation technology, especially in the fields of 3D printing, powder metallurgy and thermal spraying technology, the demand and requirements for metal powder are getting higher and higher. Metal powder production methods include chemical, physical and mechanical methods. Among them, the gas atomization method in the physical method is widely used in actual production because of its advantages such as low production cost, high production efficiency, high powder quality, and good controllability. In gas atomization powder making technology, electrode induction melting gas atomization (electrode induction melting gas atomization, EIGA) powder mak...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B22F9/08B22F1/00
CPCB22F9/082B22F2009/0824B22F2009/0848B22F1/142
Inventor 谭小练李传锋王录全郭振陈勇周成元刘云明
Owner NUCLEAR POWER INSTITUTE OF CHINA
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