Method for displaying thermal deformation texture of steel used for nuclear power pressure container

A technology of pressure vessel and display method, applied in the field of display of thermal deformation structure of steel for nuclear power pressure vessel, can solve problems such as difficult display, and achieve the effect of clear and complete grains and optimized thermal deformation process

Active Publication Date: 2012-02-15
INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a simple and efficient display method for clearly displaying the original austenite grains after thermal deformation of steel for nuclear power pressure vessels, and it is difficult to solve the problem of prior

Method used

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  • Method for displaying thermal deformation texture of steel used for nuclear power pressure container
  • Method for displaying thermal deformation texture of steel used for nuclear power pressure container
  • Method for displaying thermal deformation texture of steel used for nuclear power pressure container

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0028] 1. Preparation of Thermally Deformed Samples

[0029] a) Machining of the sample: the nuclear power pressure vessel is machined into a small cylinder with a diameter of 8mm and a height of 15mm, the surface is polished, and the surface finish is at above.

[0030] b) Thermal deformation process: The cylindrical sample is thermally compressed and deformed on a thermal simulator. The deformation temperature is 900°C, the strain rate is 0.1 / s, and the strain is 70% (the corresponding true strain is 1.2). Immediately after the deformation Samples were removed and quenched into water.

[0031] c) Cutting and inlaying of metallographic samples: use wire electric discharge cutting to divide the hot-deformed and quenched cake-shaped sample into two along the direction of the central axis, and take the central longitudinal section of the thermally-deformed sample as the metallographic observation surface for inlaying , in preparation for subsequent metallographic sample prepa...

Embodiment 2

[0044] The difference from Example 1 is:

[0045] 1. Preparation of Thermally Deformed Samples

[0046] a) Machining of the sample: the nuclear power pressure vessel is machined into a small cylinder with a diameter of 8mm and a height of 15mm, the surface is polished, and the surface finish is at above.

[0047] b) Thermal deformation process: The cylindrical sample is thermally compressed and deformed on a thermal simulator. The deformation temperature is 1000°C, the strain rate is 10 / s, and the strain is 70% (the corresponding true strain is 1.2). Samples were removed and quenched into water.

[0048] c) Cutting and inlaying of metallographic samples: use wire electric discharge cutting to divide the hot-deformed and quenched cake-shaped sample into two along the direction of the central axis, and take the central longitudinal section of the thermally-deformed sample as the metallographic observation surface for inlaying , in preparation for subsequent metallographic sa...

Embodiment 3

[0059] The difference from Example 1 is:

[0060] 1. Preparation of Thermally Deformed Samples

[0061] a) Machining of the sample: the nuclear power pressure vessel is machined into a small cylinder with a diameter of 8mm and a height of 15mm, the surface is polished, and the surface finish is at above.

[0062] b) Thermal deformation process: The cylindrical sample is thermally compressed and deformed on a thermal simulator. The deformation temperature is 1100°C, the strain rate is 10 / s, and the strain is 70% (the corresponding true strain is 1.2). Immediately after the deformation Samples were removed and quenched into water.

[0063] c) Cutting and inlaying of metallographic samples: use wire electric discharge cutting to divide the hot-deformed and quenched cake-shaped sample into two along the direction of the central axis, and take the central longitudinal section of the thermally-deformed sample as the metallographic observation surface for inlaying , in preparatio...

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Abstract

The invention relates to the metallic phase sample preparation and austenite crystal grain display technical field, concretely relates to a method for displaying original austenite crystal grains obtained by performing thermal deformation to a low carbon low alloy steel used for a nuclear power pressure container, and is used for solving the problem for displaying thermal deformation texture austenite crystal grain of SA 508-3 steel used for the nuclear power pressure container. The method of the invention comprises the steps of preparing a thermal deformation sample, grinding and polishing the metallographic sample, chemically etching the sample and mechanically polishing by selectivity. According to the reasonable ratio of a supersaturated picric acid solution to paste shampoo (the weight ratio of the picric acid to paste shampoo is 1:1) and the selection of the water-bath temperature (80-90 DEG C) and corrosion time (3-5 minutes), the original austenite crystal grain of a quenched texture obtained by performing the thermal deformation on SA 508-3 steel at the temperature of 800-1200 DEG C can be clearly displayed, and the method provides an important foundation for researching the recrystallization rule of the steel used for the nuclear power pressure container and optimizing the thermal deformation technology of the steel used for the nuclear power pressure container.

Description

technical field [0001] The invention relates to the technical field of metallographic sample preparation and austenite grain display, in particular to a method for displaying original austenite grains after thermal deformation of low-carbon low-alloy steel used in nuclear power pressure vessels. In the process of evaluating the original austenite structure after deformation temperature deformation, clear and complete original austenite grain boundaries can be obtained, so as to obtain accurate statistical results of grain size. Recrystallization rules provide convenience. Background technique [0002] At present, SA508-3 steel is the main material of large pressure vessels such as nuclear power reactor pressure vessels, steam generators, and voltage stabilizers. It belongs to low-carbon and low-alloy bainite steel (see Table 1 for composition). As we all know, the reactor pressure vessel has a large volume and high weight, and belongs to (extra) large forgings. With the in...

Claims

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Application Information

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IPC IPC(8): G01N1/28G01N1/32
Inventor 郝露菡孙明月李殿中
Owner INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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