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Zr-Sn-Nb合金1000~1250℃蒸汽氧化后的微观组织
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1.西北工业大学;2.西北有色金属研究院

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国家自然科学基金(No. 51572224),高等学校学科创新引智计划(BP0820014),国防基础科研计划(WDYX19614260201)


Microstructure of Oxidized Zr-Sn-Nb Alloy after 1000~1250℃ Steam
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    摘要:

    锆合金包壳管在核反应堆失水事故时发生高温蒸汽氧化而脆化破裂,该过程与锆合金的微观组织变化密切相关,因此,本文开展了Zr-Sn-Nb包壳管在1000~1250℃的蒸汽氧化试验,使用光学显微镜、扫描电子显微镜、透射电子显微镜等分析蒸汽氧化后的微观组织,并使用氧氮氢分析仪研究了氢含量的变化规律。结果表明:Zr-Sn-Nb合金蒸汽氧化层分为ZrO2、α-Zr(O)和Prior-β层。随蒸汽氧化时间增加,ZrO2和α-Zr(O)层厚度增加,同时α-Zr(O)层中的裂纹逐渐增多,Prior-β层中残留的β-Zr逐渐转变为片状α-Zr,且α-Zr晶粒宽度不断增加。1000℃蒸汽氧化形成疏松的ZrO2层,存在大量横向贯穿裂纹,1150~1250℃蒸汽氧化后的ZrO2层较为致密。蒸汽氧化后,Zr-Sn-Nb合金基体的吸氢量随蒸汽氧化时间增加而增加,1000℃蒸汽氧化的吸氢量远高于其它温度。1000℃蒸汽氧化后,α-Zr基体与氢化物取向关系为(0002)α-Zr//(-20-2)δ-ZrH1.66,[2-1-10]α-Zr//[011]δ-ZrH1.66;1200℃时,二者的取向关系为(-2110)α-Zr//(20-2)δ-ZrH1.66,[01-10]α-Zr//[111]δ-ZrH1.66。

    Abstract:

    During the loss-of-water accident in the nuclear reactor, the high-temperature steam can react with the Zr alloy cladding tube and lead to oxidation of the Zr alloys, which lead to the embrittlement and fracture of the cladding tube. The process is closely related to the microstructural evolution of the Zr alloys. In order to reveal the embirttlement mechanisms of the Zr-Sn-Nb cladding tube, the steam oxidation experiments of Zr-Sn-Nb alloy at 1000~1250 ℃ were performed. The microstructure was investigated by an optical microscope, a scanning electron microscope and a transmission electron microscope. The hydrogen content was identified by a oxygen, nitrogen and hydrogen analyzer. The results show that the Zr-Sn-Nb alloy can be oxidized into three layers, including ZrO2, α-Zr(O) and Prior-β. The thickness of ZrO2 layer and α-Zr(O) layer increase with increasing oxidation time, meanwhile, the number of cracks increase in α-Zr(O) layer. The lath β-Zr phase of the Prior-β layer is transformed into sheet-like α-Zr phase and grain width of α-Zr phase become larger when the alloy is exposed to longer steam oxidation time. Loose ZrO2 layer with a large number of transverse cracks can be formed in 1000℃ steam, while dense ZrO2 layer can be observed at higher temperatures. H content of the Zr-Sn-Nb alloy matrix increases with the oxidation time. The hydrogen pickup of the Zr-Sn-Nb alloy matrix is much higher at 1000°C steam than those at other temperatures. The orientation relationship between the α-Zr matrix and the hydride is (0002)α-Zr//(-20-2)δ-ZrH1.66 and [2-1-10]α-Zr//[011]δ-ZrH1.66 in 1000℃ steam, and (-2110)α-Zr//(20-2)δ-ZrH1.66 and [01-10]α-Zr//[111]δ-ZrH1.66 in 1200℃ steam.

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张瑶,应雯清,程赞粼,张锋,王彦峰,王少鹏,张程煜. Zr-Sn-Nb合金1000~1250℃蒸汽氧化后的微观组织[J].稀有金属材料与工程,2022,51(11):4173~4179.[zhangyao, yingwenqing, chengzanlin, zhangfeng, wangyanfeng, wangshaopeng, zhangchengyu. Microstructure of Oxidized Zr-Sn-Nb Alloy after 1000~1250℃ Steam[J]. Rare Metal Materials and Engineering,2022,51(11):4173~4179.]
DOI:10.12442/j. issn.1002-185X.20210878

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  • 收稿日期:2021-10-10
  • 最后修改日期:2022-02-10
  • 录用日期:2022-02-10
  • 在线发布日期: 2022-12-02
  • 出版日期: 2022-11-30