首页|Fe+Cr及Si含量对Zr-4合金耐腐蚀性能的影响

Fe+Cr及Si含量对Zr-4合金耐腐蚀性能的影响

Effect of Fe+Cr and Si Contents on Corrosion Resistance of Zircaloy-4

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为了优化国产Zr-4合金的耐腐蚀性能,在420℃、10.3 MPa的高温高压水蒸气加速腐蚀条件下,研究了合金元素Fe+Cr以及杂质元素Si对国产Zr-4合金耐腐蚀性能的影响.结果表明:在美国材料实验学会(ASTM)规定的Fe+Cr含量范围内(0.28 wt%~0.37 wt%,wt%表示质量分数),Fe+Cr含量越高,析出的第二相数目越多、尺寸越大,越有利于材料耐腐蚀性能提升.在420℃水蒸气中腐蚀126 d后,当Fe+Cr含量从0.28 wt%增加到0.37 wt%时,Zr-4合金的腐蚀增重降低约30%.Zr-4合金在1100℃淬火时,当Si含量低至10mg/kg时,形成粗大的平行板条结构;而增加Si含量到100mg/kg后,析出的细小Zr3Si为α相提供形核位置,使得组织中出现网篮结构和细小的平行板条结构.网篮结构能促使组织中第二相分布更均匀弥散,因此,高Si含量的Zr-4合金表现出更优良的耐腐蚀性能.
In order to optimize the corrosion resistance of domestic Zr-4 alloy,the effects of alloying element Fe+Cr and impurity element Si on the corrosion resistance of domestic Zr-4 alloy were studied under the accelerated corrosion condition of high temperature and high pressure steam at 420℃ and 10.3 MPa.The results show that within the range of Fe+Cr content specified by ASTM(0.28 wt%-0.37 wt%,with wt%representing mass percentage),the higher the Fe+Cr content,the larger the number and size of the precipitated second phases,which is beneficial to the improvement of the corrosion resistance of the material.When the content of Fe+Cr increases from 0.28 wt%to 0.37 wt%,the corrosion weight gain of Zr-4 alloy decreases by about 30%after 126 d of corrosion in steam at 420 ℃.When the Si content of Zr-4 alloy is as low as 10 mg/kg during quenching at 1100℃,the coarse parallel-plate structure is formed.When the Si content is increased to 100 mg/kg,the precipitated fine Zr3Si provides nucleation sites for α phase,which leads to the appearance of basketweave structure and fine parallel-plate structure in the microstructure.The basketweave structure can promote the distribution of the second phase in the structure to be more uniform and diffuse,so the Zr-4 alloy with high Si content shows better corrosion resistance.

Zr-4 alloyFe+Cr contentSi contentCorrosion resistance

岳慧芳、庞华、高博、高士鑫、罗倩倩、赵艳丽、蒋有荣

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中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213

国核宝钛锆业股份公司陕西省核级锆材重点实验室,陕西宝鸡,721013

Zr-4合金 Fe+Cr含量 Si含量 耐腐蚀性能

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(3)
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