Cladding material zirconium alloy for small-sized water-cooled nuclear reactor and manufacturing method

Abstract

The invention provides a cladding material zirconium alloy for a small-sized water-cooled nuclear reactor. The zirconium alloy comprises the following chemical components, in percentage by weight, of0.80%-1.10% of Sn, 0.25%-0.50% of Fe, 0.10%-0.30% of Cr, 0.08%-0.16% of O, one or two of 0.02%-0.09% of Nb and 0.01%-0.05% of Ni, as well as the balance Zr. According to the cladding material zirconium alloy, the problem of nodular corrosion of a conventional zirconium alloy in oxygen-containing water is effectively solved, the uniform corrosion resistance is better, meanwhile, the factors which bring harmful effects to the corrosion resistance of the zirconium alloy are actively eliminated, and the safety and reliability of a nuclear power station are improved.

Description

technical field [0001] The invention relates to the field of structural materials for fuel cladding and spacer grid strips, in particular to zirconium alloys for fuel cladding and spacer grid strips and other structural materials for small water-cooled nuclear reactor nuclear power plants. Background technique [0002] Due to the advantages of flexibility and versatility of small nuclear reactors, countries around the world pay more and more attention to the development of small nuclear reactors. Judging from the trend of developing small reactors in countries around the world, water-cooled nuclear reactors are the main type of small reactors. The nuclear fuel element is the core component of the small reactor, and its performance is directly related to the advancement, safety and economy of the small reactor. Therefore, it is crucial to develop nuclear fuel elements suitable for the further development of small reactors. [0003] In some water-cooled nuclear power reactor...

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Problems solved by technology

The hot forming temperature adopted is above 780°C. During the hot forming process, the N18 zirconium alloy will inevitably enter the dual-phase region, which will cause uneven distribution of alloy components after heating in the dual-phase region, resulting in deterioration of uniform corrosion resistance. and furuncle corrosion, which will have a detrimental effect on the corrosion resistance of zirconium alloys

[0008] In summary, the composition of Zr-4 alloy is not in the optimal range, the processing window is narrow, and it is difficult to take into account both uniform corrosion resistance and boil corrosion resistance; Zr-2 alloy absorbs hydrogen strongly; and Zr- 2 and Zr-4 alloys cannot meet the requirements of high burnup fuel assemblies

High Nb zirconium alloys such as ZIRLO, E110, E635, and M5 can meet the requirements of high burnup fuel components in pressurized water reactor nuclear power plants, but the corrosion resistance of high Nb zirconium alloys is very sensitive to dissolved oxygen, and they are resistant to corrosion in water with high dissolved oxygen Significantly worse performance

The α→β phase transition temperature of the N18 alloy with low Nb is lower than that of Zr-4, and the components will inevitably enter the dual-phase region during hot forming, which will have a harmful impact on the corrosion resistance of the zirconium alloy; In addition, the corrosion resistance of zirconium alloys containing Nb in high oxygen water is not as good as Zr-2 and Zr-4 alloys of Zr-Sn series

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