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壓水堆燃料包殼鋯合金中第二相腐蝕行為研究進展
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作者單位:

1.上海大學(xué) 材料研究所;2.上海大學(xué) 分析測試中心

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基金項目:

國家自然科學(xué)基金青年項目(No. 51901123和No. 52001192)


Research Progress on Corrosion Behavior of Secondary Phase Precipitate of Zirconium Alloy Fuel Cladding in Pressurized Water Reactor
Author:
Affiliation:

1.Institute of Materials,Shanghai University,Shanghai;2.Laboratory for Microstructures,Shanghai University,Shanghai;3.I nstitute of Materials,Shanghai University,Shanghai

Fund Project:

The National Natural Science Foundation of China （Youth program）(No. 51901123 & No. 52001192)

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    摘要:

    鋯合金是目前唯一大規(guī)模商用的壓水堆燃料包殼材料,其耐水側(cè)腐蝕性能是影響核反應(yīng)堆安全性與經(jīng)濟性的重要因素。微量合金元素(Fe、Nb等)主要以第二相的形式彌散分布在鋯合金基體中,但可對鋯合金的腐蝕行為產(chǎn)生顯著影響。本文比較了不同鋯合金中第二相的差異,綜述了鋯合金中典型第二相的腐蝕行為及其影響因素。分別比較了二元及三元第二相中主要合金元素Fe和Nb的腐蝕過程,總結(jié)了不同水化學(xué)條件下第二相腐蝕產(chǎn)物的差異及其對鋯合金基體腐蝕行為的影響,并指出當前針對第二相腐蝕行為研究中存在的不足。最后,對鋯合金第二相腐蝕行為研究趨勢進行了展望,先進微觀表征手段可進一步完善含F(xiàn)e、Nb元素第二相的腐蝕機理研究,將為提高我國新型鋯合金包殼材料的耐腐蝕性能提供理論參考。

    Abstract:

    Zirconium alloy is the one and only fuel cladding material for pressurized water reactor (PWR) in full-scale commercial use at present, and its water-side corrosion resistance is the dominant factor for the safety and economy of nuclear reactor. The trace alloying elements (Fe, Nb etc.) are existed in zirconium matrix in the form of dispersive secondary phase precipitates (SPPs), which has a crucial influence on the corrosion behavior of zirconium alloy. The type of SPP for various zirconium alloys was compared in this article, and then the corrosion behaviors and influence factors of typical SPPs were reviewed. The corrosion procedures of principal alloying elements Fe and Nb within the binary and/or ternary SPPs were compared respectively, and the difference of SPP corrosion products under different water chemistry and the further effects on the corrosion behavior of zirconium matrix were also summerized. Meanwhile, the deficiencies of current studies on SPP corrosion behavior were indicated. Finally, the future research vision of SPP in zirconium alloy was enunciated herein, and advanced microstructure characterization methods will further refine the mechanism study on corrosion of SPPs bearing Fe and/or Nb, which will provide theoretical support for the corrosion resistance improvement of domestic novel zirconium cladding materials.

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王德鵬,李毅豐,梁雪,彭劍超,李強,姚美意,周邦新.壓水堆燃料包殼鋯合金中第二相腐蝕行為研究進展[J].稀有金屬材料與工程,2023,52(2):753~762.[Wang Depeng, Li Yifeng, Liang Xue, Peng Jianchao, Li Qiang, Yao Meiyi, Zhou Bangxin. Research Progress on Corrosion Behavior of Secondary Phase Precipitate of Zirconium Alloy Fuel Cladding in Pressurized Water Reactor[J]. Rare Metal Materials and Engineering,2023,52(2):753~762.]
DOI：10.12442/j. issn.1002-185X.20220059

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歷史
  • 收稿日期:2022-01-20
  • 最后修改日期:2022-03-11
  • 錄用日期:2022-03-28
  • 在線發(fā)布日期: 2023-03-09
  • 出版日期: 2023-02-28