一种核电用高耐蚀性高碳奥氏体不锈钢及其制造方法

By designing a high Mn and low Ni composition and combining Nb and Zr, along with specific metallurgical processes, a high-corrosion-resistant high-carbon austenitic stainless steel was prepared. This solved the problem of insufficient strength and corrosion resistance in nuclear power equipment, achieving high strength and excellent corrosion resistance, and meeting the comprehensive performance requirements of nuclear power equipment.

CN116732452BActive Publication Date: 2026-07-17ANGANG STEEL CO LTD
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
ANGANG STEEL CO LTD
Filing Date
2023-05-30
Publication Date
2026-07-17

AI Technical Summary

Technical Problem

Existing austenitic stainless steels are not strong enough in the nuclear power field, making it difficult to meet the requirements of large-scale equipment and high temperature and pressure. At the same time, their cavitation resistance is insufficient, and they cannot effectively prevent material fatigue damage and surface erosion.

Method used

By employing a high Mn and low Ni composition design, combined with the combined effects of Nb and Zr, and the synergistic effects of Cr, Mn, Co, and Si, a high corrosion-resistant high-carbon austenitic stainless steel is prepared through a process of smelting, continuous casting, heating, rolling, straightening, slow cooling, and heat treatment, ensuring that the steel plate has high strength and good corrosion resistance.

Benefits of technology

The steel plate has a room temperature yield strength and tensile strength of 530MPa and 735MPa or higher, respectively; a high temperature tensile strength of 325MPa and 527MPa or higher, respectively; a low temperature impact energy of -20℃ of 150J or higher; and a cumulative weight loss of ≤2.53mg after a 40h vibration cavitation test, thus meeting the comprehensive performance requirements of nuclear power equipment.

✦ Generated by Eureka AI based on patent content.

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Abstract

本发明公开了一种核电用高耐蚀性高碳奥氏体不锈钢及其制造方法，钢的化学成分包含C：0.20％‑0.35％；Si：2.0％‑3.0％；Mn：5.50％‑7.50％；P≤0.015％；S≤0.005％；Ni：3.80％‑4.50％；Cr：16.75％‑18.25％；Co：0.75％‑1.00％，Nb：0.10％‑0.20％；Zr：0.05％‑0.08％。配合冶炼、连铸、加热、轧制、热处理的工艺生产，保证了钢板具有较高的综合性能水平，室温屈服强度(Rp0.2)和抗拉强度(Rm)分别达到530MPa和735MPa以上；550℃高温拉伸时，屈服强度(Rp0.2)和抗拉强度(Rm)分别达到325MPa和527MPa以上；‑20℃低温冲击时，冲击功达到150J以上，同时40h振动空蚀试验后，累计失重量≤2.53mg，具有优异的耐蚀性能。
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