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Heat treatment method for austenitic stainless steel pie forgings for nuclear power reactor internals

A technology of austenitic stainless steel and heat treatment method, applied in the field of heat treatment, can solve the problems of poor bottom performance of forgings, deterioration of forging performance uniformity, etc., achieve uniform performance, uniform structure, and ensure overall quality

Active Publication Date: 2014-05-28
SHANGHAI ELECTRIC SHMP CASTING & FORGING CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Practice has shown that if effective measures are not taken, the temperature difference between the bottom and side of the forging can reach hundreds of degrees during the simultaneous cooling process, resulting in poor performance at the bottom of the forging and worsening the uniformity of the forging performance

Method used

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  • Heat treatment method for austenitic stainless steel pie forgings for nuclear power reactor internals
  • Heat treatment method for austenitic stainless steel pie forgings for nuclear power reactor internals

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Embodiment Construction

[0019] Such as figure 1 As shown, the heat treatment method of the austenitic stainless steel pie-shaped forging for nuclear power reactor internal components of the present invention is used to heat treat a solid forging with a material of 0Cr19Ni10, a diameter of not less than 4000mm, and a thickness of not less than 400mm, comprising the following steps:

[0020] The first step is to place the forging in a heat treatment furnace and heat it to a temperature range of 400-450°C with the maximum power of the heat treatment furnace. The heat preservation time is 0.5-1 minute per 1 mm of forging thickness;

[0021] The purpose of this step is to control the temperature difference between the surface and the core of the forging to avoid cracking of the forging caused by blue embrittlement;

[0022] The second step is to continue to heat the workpiece, and heat the forging to a temperature range of 670-700 °C at a heating rate of no more than 50 °C / h. The holding time is 0.5-1 min...

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Abstract

The invention discloses a heat treatment method for austenitic stainless steel pie forgings for nuclear power reactor internals. The method is used for performing heat treatment on a solid forging, the material of the solid forging is 0Cr19Ni10, the diameter of the material is not smaller than 4000 mm, and the thickness of the material is not smaller than 400 mm. The method comprises the following steps: step 1, heating the forging to 400-450 DEG C for preserving heat by using the maximum power of a heat treatment furnace, wherein the preserving heat time is 0.5-1 minute for each millimeter of forging thickness; step 2, heating the forging to 670-700 DEG C for preserving heat at the temperature rise rate of at most 50 DEG C / h, wherein the preserving heat time is 0.5-1 minute for each millimeter of forging thickness; step 3, heating the forging to 1040-1080 DEG C for preserving heat at the temperature rise rate of at most 150 DEG C / h, wherein the preserving heat time is 3-5 minutes for each millimeter of forging thickness; step 4, discharging the forging from the furnace and cooling with water. The crystalline grains of the 0Cr19Ni10 steel forging subjected to heat treatment by the method are not grown, organization is uniform, and the strength of room temperature and 350 DEG C of high temperature meets the design requirement of the nuclear power reactor internals.

Description

technical field [0001] The invention relates to a heat treatment method, in particular to a heat treatment method for an austenitic stainless steel pie-shaped forging used for nuclear power reactor internal components. Background technique [0002] With the rapid development of the economy, the demand for energy in various countries has increased dramatically. Because nuclear fuel can release efficient and clean energy, the development and utilization of nuclear energy has been promoted. Compared with other earlier reactor types, the AP1000 nuclear power stack has the characteristics of large-scale and integrated, and the size and weight of the internal components of the nuclear power main equipment are correspondingly larger. [0003] The reactor internals sit at the center of the reactor and provide support and compression for the nuclear fuel assembly, while also shielding the pressure vessel from the effects of radiation. The austenitic stainless steel pie-shaped forgi...

Claims

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Application Information

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IPC IPC(8): C21D11/00C21D9/00
Inventor 靳海山曹胜强龙智南林岳萌
Owner SHANGHAI ELECTRIC SHMP CASTING & FORGING CO LTD
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