High-purity austenitic stainless steel for nuclear power and preparation method and application thereof

By preparing low-cobalt nickel-iron alloy liquid, primary refining in an AOD furnace, refining in an LF furnace, and ESR treatment, combined with gradient solution treatment, the problems of high cobalt content, excessive gas content, and structural defects in stainless steel for nuclear power applications have been solved, achieving efficient and low-cost preparation of high-purity austenitic stainless steel.

CN120608239BActive Publication Date: 2026-07-24GUANGDONG GUANGQING METAL TECH +2
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
GUANGDONG GUANGQING METAL TECH
Filing Date
2025-06-30
Publication Date
2026-07-24

AI Technical Summary

Technical Problem

Existing technologies for manufacturing stainless steel for nuclear power plants suffer from inadequate control of impurity elements, high cobalt content, excessive gas content, significant structural defects, low process efficiency, and high costs.

Method used

Low-cobalt nickel-iron alloy liquid was prepared by using low-cobalt laterite nickel ore and low-cobalt iron ore powder. Combined with AOD furnace primary refining, LF furnace refining and ESR treatment, yttrium oxide was used to reduce the cobalt and oxygen content. Continuous casting and ESR were used to replace die casting. Gradient solution treatment was adopted to achieve uniform microstructure.

Benefits of technology

Significantly reduced cobalt content, better gas purification effect, improved microstructure uniformity, enhanced process efficiency, and reduced cost meet the demand for high-purity, high-performance stainless steel for nuclear power applications.

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Abstract

The application relates to a high-purity austenitic stainless steel for nuclear power, and a preparation method and application thereof. In the preparation method, Co content is reduced from the source by screening low-Co raw materials; the effects of efficiently removing [H] and T[O] and reducing inclusion size are realized by selecting an AOD-LF-continuous casting-ESR purification process; the ferrite content in the stainless steel is reduced, the segregation band is reduced, and the process time is shortened by taking the continuous casting blank as an ESR consumable electrode; the grain uniformity is obviously improved by high-pressure rolling and gradient solid solution treatment on the plate, so that the level difference between the center and the surface layer of the stainless steel is less than or equal to 1. The preparation method significantly improves the purity, service performance and production efficiency of the stainless steel material, and is suitable for nuclear reactor pressure vessel internal components.
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