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粉末冶金法制备核燃料包壳FeCrAl合金研究进展

贾文清,  刘向兵,  徐超亮,  李远飞,  钱王洁,  全琪炜,  尹建

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贾文清, 刘向兵, 徐超亮, 李远飞, 钱王洁, 全琪炜, 尹建. 粉末冶金法制备核燃料包壳FeCrAl合金研究进展[J]. 粉末冶金技术, 2022, 40(1): 22-32. doi: 10.19591/j.cnki.cn11-1974/tf.2021060010
引用本文: 贾文清, 刘向兵, 徐超亮, 李远飞, 钱王洁, 全琪炜, 尹建. 粉末冶金法制备核燃料包壳FeCrAl合金研究进展[J]. 粉末冶金技术, 2022, 40(1): 22-32. doi: 10.19591/j.cnki.cn11-1974/tf.2021060010
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JIA Wen-qing, LIU Xiang-bing, XU Chao-liang, LI Yuan-fei, QIAN Wang-jie, QUAN Qi-wei, YIN Jian. Research progress on FeCrAl alloys used for nuclear fuel cladding prepared by powder metallurgy[J]. Powder Metallurgy Technology, 2022, 40(1): 22-32. doi: 10.19591/j.cnki.cn11-1974/tf.2021060010
Citation: JIA Wen-qing, LIU Xiang-bing, XU Chao-liang, LI Yuan-fei, QIAN Wang-jie, QUAN Qi-wei, YIN Jian. Research progress on FeCrAl alloys used for nuclear fuel cladding prepared by powder metallurgy[J]. Powder Metallurgy Technology, 2022, 40(1): 22-32. doi: 10.19591/j.cnki.cn11-1974/tf.2021060010
shu

粉末冶金法制备核燃料包壳FeCrAl合金研究进展

doi: 10.19591/j.cnki.cn11-1974/tf.2021060010

  • 苏州热工研究院有限公司，苏州 215004

基金项目: 国家自然科学基金资助项目（U1867215，12075274）；广东省基础与应用基础研究重大项目（2019B030302011）
详细信息
    通讯作者:

    E-mail: liuxbing@cgnpc.com.cn

  • 中图分类号: TL341

Research progress on FeCrAl alloys used for nuclear fuel cladding prepared by powder metallurgy

  • Suzhou Nuclear Power Research Institute, Suzhou 215004, China

More Information

    摘要
  • 摘要: 燃料包壳是核反应堆安全运行的重要保障。福岛核事故后，国内外开展了大量新型事故容错燃料包壳的研发工作。由于具有抗高温氧化和高强度等优异的综合性能，FeCrAl合金已成为新一代事故容错燃料包壳的重要候选材料之一。经过多年积累，核燃料包壳FeCrAl合金的设计和制备研究已取得一定进展。利用粉末冶金方法制备性能更为优异的氧化物弥散强化FeCrAl合金前景广阔，受到国内外学者的广泛关注。本文综述了核燃料包壳FeCrAl合金的成分设计、熔炼制备和粉末冶金制备的研究现状，分析了不同方法制备合金的组织性能及存在的问题，对未来核燃料包壳FeCrAl合金的设计和制备进行了展望。
    Abstract: The fuel cladding plays an important role for the safe operation of the nuclear reactors. After the Fukushima nuclear accident, a large number of new types of the accident-tolerant fuel cladding have been developed. FeCrAl alloys have become one of the important candidate materials for the new generation of the accident-tolerant fuel cladding due to the excellent comprehensive properties, such as the high temperature oxidation resistance and the high strength. After years of research and development, some progress has been made in the design and preparation of FeCrAl alloys used for the nuclear fuel cladding. As one of the main research directions, the preparation of the oxide dispersion strengthened FeCrAl alloys with the better performance by powder metallurgy shows a broad prospect and has attracted the extensive attention from scholars at home and abroad. In this paper, the research status of the composition design, smelting, and powder metallurgy for the FeCrAl alloys used for the nuclear fuel cladding were reviewed. The microstructure, properties, and the existing problems of the FeCrAl alloys prepared by the different methods were analyzed. The future design and preparation of the FeCrAl alloys used for the nuclear fuel cladding were prospected.
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  • 图  1  核燃料包壳FeCrAl合金成分设计范围[11]

    Figure  1.  Composition design range of the FeCrAl alloys used for the nuclear fuel cladding[11]

    下载: 全尺寸图片 幻灯片

    图  2  添加不同元素对FeCrAl合金力学性能的影响[5]

    Figure  2.  Mechanical properties of the FeCrAl alloys added by the different elements[5]

    下载: 全尺寸图片 幻灯片

    图  3  FeCrAl合金第二相表征[2]：（a）C35MC；（b）C35MNC；（c）C35MN

    Figure  3.  Second phase characterization in FeCrAl alloys[2]: (a) C35MC; (b) C35MNC; (c) C35MN

    下载: 全尺寸图片 幻灯片

    图  4  制备成形的FeCrAl合金管材（a）和管材截面金相组织（b）[37]

    Figure  4.  FeCrAl tubes fabricated by the tube drawing (a) and the cross-section optical micrograph of the FeCrAl tube (b)[37]

    下载: 全尺寸图片 幻灯片

    图  5  机械合金化和热挤压方法制备氧化物弥散强化FeCrAl合金示意图[44]

    Figure  5.  Schematic of ODS FeCrAl Alloy Manufacturing process by mechanical alloying and hot extrusion[44]

    下载: 全尺寸图片 幻灯片

    图  6  热等静压制备工艺流程[51]

    Figure  6.  Schematic of the basic HIP production process[51]

    下载: 全尺寸图片 幻灯片

    图  7  MA957合金的金相组织：（a）原始状态；（b）1300 ℃退火1 h；（c）1300 ℃退火24 h[57]

    Figure  7.  Optical micrographs of MA957: (a) as-received condition; (b) annealing for 1 h at 1300 ℃; (c) annealing for 24 h at 1300 ℃[57]

    下载: 全尺寸图片 幻灯片

    图  8  常规熔炼FeCrAl合金（a）与热等静压法制备APMT合金（b）中子辐照前后拉伸曲线 [22]

    Figure  8.  Tensile curves before and after the neutron irradiation for FeCrAl alloys by melting method (a) and APMT alloys by HIP (b)[22]

    下载: 全尺寸图片 幻灯片

    图  9  不同机制的强化效果随温度的变化[68]

    Figure  9.  Temperature dependency of the strengthening effects in the different mechanisms [68]

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    图  10  放电等离子烧结（a）和热等静压方法（b）制备FeCrAl合金抛光组织对比[70]

    Figure  10.  Polishing images of the SPS (a) and HIP (b) FeCrAl samples[70]

    下载: 全尺寸图片 幻灯片

    表  1  不同方法制备FeCrAl合金晶粒尺寸与拉伸性能

    Table  1.   Grain size and tensile properties of the FeCrAl alloy prepared by various methods

    制备方法平均晶粒尺寸 / μm拉伸强度 / MPa参考文献
    室温300 ℃
    传统熔炼法电弧熔炼/真空感应熔炼20～500459～811377～680[2, 76]
    粉末冶金法热挤压0.3～4.61117～13161150[19‒20, 30, 49]
    热等静压36～150550～960400～800[2, 55]
    放电等离子烧结1.6730～16421477[68, 70]
    选择性激光烧结0.5～50.0400～600—[53, 73]
    下载: 导出CSV
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  • 收稿日期:  2021-06-25
  • 刊出日期:  2022-02-28

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