Production method of nuclear austenitic stainless steel with controlled cobalt content

A technology of austenitic stainless steel and production method, which is applied in the field of production of nuclear austenitic stainless steel to control the cobalt content, can solve problems such as being unable to meet the use requirements of nuclear austenitic stainless steel, and achieve reduction of smelting energy consumption cost, tons The effect of steel cost reduction and energy consumption cost reduction

Active Publication Date: 2020-03-27
GANSU JIU STEEL GRP HONGXING IRON & STEEL CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, the conventional smelting method of austenitic stainless steel is the production process of EAF+AOD+LF+CCM. The smelting analysis of austenitic stainless steel smelted by this method generally has Co>0.20%, which cannot meet the requirements of nuclear austenitic stainless steel.

Method used

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  • Production method of nuclear austenitic stainless steel with controlled cobalt content
  • Production method of nuclear austenitic stainless steel with controlled cobalt content
  • Production method of nuclear austenitic stainless steel with controlled cobalt content

Examples

Experimental program
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Effect test

Embodiment 1

[0049] Step 1, raw material preparation: 114t of nuclear austenitic stainless steel molten steel smelted in this embodiment requires 70t of dephosphorized molten iron, 38t of ferrochrome, and 9.1t of electrolytic nickel, wherein the chemical compositions of dephosphorized molten iron, ferrochrome and electrolytic nickel are as follows Table 1 shows.

[0050] Table 1 Chemical composition of dephosphorized hot metal, ferrochrome and electrolytic nickel in Example 1

[0051]

[0052] Step 2. AOD process control: smelting in a furnace with a furnace age of 50, AOD reduction slag alkalinity 2.0, desulfurization stage alkalinity 3.0, slag dumping after reduction, ladle slag amount 250mm.

[0053] Step 3, LF treatment process: After the slag is pulled into the station, the temperature is measured at 1578°C, and after 5 minutes of power transmission, 85kg of electrolytic nickel and 210kg of ferrochrome are added, and the temperature is measured again at 1582°C. Blow for 12 minutes...

Embodiment 2

[0056] Step 1, raw material preparation: 110t of nuclear austenitic stainless steel molten steel smelted in this embodiment requires 68t of dephosphorized molten iron, 37t of ferrochrome, and 8.9t of electrolytic nickel, wherein the chemical compositions of dephosphorized molten iron, ferrochrome and electrolytic nickel are as follows Table 2 shows.

[0057] Chemical composition of dephosphorized hot metal, ferrochrome and electrolytic nickel in Table 2 Example 2

[0058]

[0059] Step 2, AOD process control: smelting with a furnace age of 20 furnaces, AOD reduction slag alkalinity 1.9, desulfurization stage alkalinity 2.5, slag dumping after reduction, ladle with slag 200mm.

[0060] Step 3, LF treatment process: After removing slag, enter the station to measure the temperature at 1568°C, add 108kg of electrolytic nickel after 8 minutes of power transmission and temperature rise, measure the temperature again at 1586°C, start weak blowing for 15 minutes, and calm down for ...

Embodiment 3

[0063]Step 1. Raw material preparation: 112t of nuclear austenitic stainless steel molten steel smelted in this embodiment requires 67t of dephosphorized molten iron, 42t of ferrochrome, and 9.25t of electrolytic nickel, wherein the chemical compositions of dephosphorized molten iron, ferrochrome and electrolytic nickel are as follows Table 3 shows.

[0064] Chemical composition of dephosphorized hot metal, ferrochrome and electrolytic nickel in Table 3 Example 3

[0065]

[0066] Step 2, AOD process control: smelting with a furnace age of 80, AOD reduction slag alkalinity 1.8, desulfurization stage alkalinity 2.0, slag pouring after reduction, ladle slag amount 150mm.

[0067] Step 3, LF treatment process: After the slag is pulled into the station, the temperature is measured at 1583°C, and after 3 minutes of power transmission, 72kg of electrolytic nickel and 164kg of ferrochrome are added, and the temperature is measured again at 1582°C. Blow for 12 minutes, and cool do...

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Abstract

The invention discloses a production method of nuclear austenitic stainless steel with controlled cobalt content. The production method comprises the following steps of carrying out raw material preparation, carrying out AOD process control, refining furnace treatment and continuous casting. According to the production method, the smelted austenitic stainless steel is smelted by adopting pure molten iron, 300 series scrap steel is not added, nickel alloy adopts electrolytic nickel, the Co content of the austenitic stainless steel smelted through the method is less than or equal to 0.10%, and the use requirements of the nuclear austenitic stainless steel are met; after the blast furnace molten iron is fed into a factory, firstly, slagging-off treatment is carried out, then triple de-treatment (DDD) is carried out, desilicication and dephosphorization treatment are carried out, the pretreated molten iron is mixed into a AOD rotary furnace, and electrolytic nickel and high-carbon ferrochrome are added for production. By adopting the treatment process of the dephosphorization molten iron, the purity of the molten steel is ensured, meanwhile, due to the fact that an electric arc furnacedoes not participate in production, so that the energy consumption cost of the scheme is effectively reduced, and the cost of per ton of steel is reduced by 120 yuan/ton.

Description

technical field [0001] The invention belongs to the field of production and manufacture of austenitic stainless steel for nuclear use, and in particular relates to a production method of austenitic stainless steel for nuclear use with controlled cobalt content. Background technique [0002] The radiation sensitivity of austenitic stainless steel is relatively low, generally after 10 21 n.cm -2 The irradiation effect is obvious only after irradiation, so austenitic stainless steel is the main material for pressurized water reactor core vessel lining, heat shield, pipes, valves, etc. The radiation effect of Co element content in austenitic stainless steel is relatively large, which tends to increase the radiation embrittlement of steel. Therefore, the smelting analysis of Co requires ≤0.20%, and strives to ≤0.10%. At present, the conventional smelting method of austenitic stainless steel is the production process of EAF+AOD+LF+CCM. The smelting analysis of austenitic stainle...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C33/06C21C7/00B22D11/18C22C38/02C22C38/04C22C38/52
CPCB22D11/18C21C7/00C22C33/06C22C38/001C22C38/002C22C38/02C22C38/04C22C38/52
Inventor 高仁强陈安忠任培东李树民胡桓彰李玉峰
Owner GANSU JIU STEEL GRP HONGXING IRON & STEEL CO LTD
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