2層和厚約20nm的富鈾層形成于熱壓擴(kuò)散法制備的樣品界面。測(cè)量了合金界面擴(kuò)散系數(shù)常數(shù)和擴(kuò)散激活能,分別為4.23(±0.63)×10-6 m2/s和160.73(±1.67) kJ/mol。結(jié)果表明U-10wt.%Zr/Zr-4擴(kuò)散偶的擴(kuò)散系數(shù)大于U-Zr合金的,特別是在低溫段。"/>

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U-10Zr/Zr-4合金界面的微觀結(jié)構(gòu)及生長(zhǎng)動(dòng)力學(xué)研究
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表面物理與化學(xué)重點(diǎn)實(shí)驗(yàn)室,表面物理與化學(xué)重點(diǎn)實(shí)驗(yàn)室,表面物理與化學(xué)重點(diǎn)實(shí)驗(yàn)室,中國(guó)工程物理研究院材料研究所,中國(guó)工程物理研究院材料研究所,中國(guó)工程物理研究院材料研究所,中國(guó)科學(xué)技術(shù)大學(xué)核科學(xué)技術(shù)學(xué)院,表面物理與化學(xué)重點(diǎn)實(shí)驗(yàn)室

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國(guó)家自然科學(xué)基金項(xiàng)目（面上項(xiàng)目，重點(diǎn)項(xiàng)目，重大項(xiàng)目）,


Microstructural characterization and growth kinetics of the reaction layer in U-10wt.%Zr/Zircaloy-4 diffusion couples
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Science and Technology on Surface Physics and Chemistry Laboratory,Science and Technology on Surface Physics and Chemistry Laboratory,Science and Technology on Surface Physics and Chemistry Laboratory,Institute of Materials, China Academy of Engineering Physics,Institute of Materials, China Academy of Engineering Physics,Institute of Materials, China Academy of Engineering Physics,School of Nuclear Science and Technology,University of Science and Technology of China,Science and Technology on Surface Physics and Chemistry Laboratory

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The National Natural Science Foundation of China (General Program, Key Program, Major Research Plan)

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    摘要:

    Zr-4合金包殼包覆的U-Zr合金有望發(fā)展成為水冷反應(yīng)堆的金屬型核燃料。而燃料與包殼材料之間的相容性是反應(yīng)堆安全運(yùn)行的關(guān)鍵,但是,關(guān)于U-Zr合金燃料與Zr-4合金包殼材料界面元素?cái)U(kuò)散和反應(yīng)的研究很少。為研究U-Zr合金與Zr-4合金之間的相容性和擴(kuò)散行為,采用真空熱壓擴(kuò)散法制備U-10wt.%Zr/Zr-4擴(kuò)散偶,隨后在高真空中580-1100℃高溫?zé)崽幚順悠?。采用掃描電鏡和透射電鏡分析檢測(cè)擴(kuò)散偶的界面微觀結(jié)構(gòu)和元素分布。系統(tǒng)研究了兩種合金之間的相容性。δ-UZr2層和厚約20nm的富鈾層形成于熱壓擴(kuò)散法制備的樣品界面。測(cè)量了合金界面擴(kuò)散系數(shù)常數(shù)和擴(kuò)散激活能,分別為4.23(±0.63)×10-6 m2/s和160.73(±1.67) kJ/mol。結(jié)果表明U-10wt.%Zr/Zr-4擴(kuò)散偶的擴(kuò)散系數(shù)大于U-Zr合金的,特別是在低溫段。

    Abstract:

    U-Zr alloys cladded with Zircaloy-4 alloy are being developed as metallic fuels for water-cooled reactors. The fuel-cladding compatibility is key to the safe operation of the reactors, however, there are few studies on the interfacial reaction and diffusion of U-Zr alloys and Zircaloy-4 alloy. To investigate the compatibility and the diffusion behavior between U-Zr alloys and Zr-4 alloys, solid-to-solid U-10wt.%Zr/Zr-4 diffusion couples were assembled by vacuum hot pressing and then vacuum annealed at the temperatures range from 580 ℃ to 1100 ℃ for various time. Both scanning and transmission electron microscopy were employed for analysis of the microstructures and composition profiles at the interfaces of the couples. The compatibilities between the two alloys were systematically investigated. δ-UZr2 and ~20nm-thin U-rich layers existed in vacuum hot pressed samples. The interdiffusion coefficient constant and the activation energy were measured, which are 4.23(±0.63)×10-6 m2/s and 160.73(±1.67) kJ/mol, respectively. The interdiffusion coefficients of U-10wt.%Zr/Zr-4 alloys couples are higher than that of U-Zr alloys, especially for low temperature.

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張羽廷,王鑫,劉朋闖,曾鋼,龐曉軒,賈建平,盛六四,張鵬程. U-10Zr/Zr-4合金界面的微觀結(jié)構(gòu)及生長(zhǎng)動(dòng)力學(xué)研究[J].稀有金屬材料與工程,2018,47(9):2675~2681.[Yuting Zhang, Xin Wang, Pengchuang Liu, Gang Zeng, Xiaoxuan Pang, Jianping Jia, Liusi Sheng, Pengcheng Zhang. Microstructural characterization and growth kinetics of the reaction layer in U-10wt.%Zr/Zircaloy-4 diffusion couples[J]. Rare Metal Materials and Engineering,2018,47(9):2675~2681.]
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  • 收稿日期:2017-02-20
  • 最后修改日期:2017-07-16
  • 錄用日期:2017-08-18
  • 在線發(fā)布日期: 2018-11-01
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