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P91鋼在高流速液態鉛鉍介質中的沖蝕行為

Erosion–corrosion behaviors of P91 steel in high-velocity flowing lead–bismuth eutectic

  • 摘要: 基于第四代核能系統的發展和需求,鉛冷快中子反應堆 (Lead-cooled fast reactor, LFR) 是下一步優先發展的6種主要堆型之一. 鉛冷快堆以液態純鉛 (Lead) 或鉛鉍共晶合金 (Lead-bismuth eutectic, LBE) 作為冷卻劑,然而在高溫、高流速條件下,LBE與結構材料的沖刷腐蝕磨損嚴重限制了其工程應用. 本文以P91鋼為研究對象,在相對流速為5 m·s?1,溫度分別為350 ℃和450 ℃,不進行控氧處理的LBE中進行了3000 h的動態測試. 研究發現,350 ℃時P91鋼表面生成的氧化層為多層結構:從外到內分別為疏松的Fe3O4層、Fe–Cr尖晶石層、內氧化區 (Internal oxidation zone, IOZ),合金表面氧化層經歷了“生成—剝落—再生成”的動態平衡過程. 當介質溫度為450 ℃時,試樣表面氧化腐蝕現象更加嚴重,但是不同沖擊迎角區域的試樣表面腐蝕特征有較大差異. 試樣表面損傷的嚴重程度排序為:30° > 90° > ?90°. 30°迎角區域氧化層完全剝落,且LBE滲透入基體;90°迎角區域部分氧化層剝落,內部基體未受到LBE侵蝕;?90°迎角區域氧化層結構保持完整. 本文分析了P91鋼在高流速 (5 m·s?1) LBE中的沖蝕行為,闡明了合金氧化層的生成和剝落機制,可以為我國第四代核反應堆LFR結構或包殼材料研發及其在LBE中腐蝕機制研究提供一定實驗數據與參考.

     

    Abstract: Lead–bismuth eutectic (Pb–Bi) alloy, a liquid heavy metal, has garnered substantial attention as a candidate coolant for next-generation lead-cooled fast reactors (Gen-IV LFRs) and accelerator-driven systems (ADSs) owing to its exceptional nuclear and thermophysical properties. The demanding operational context within which these systems function poses significant challenges to the chemical and mechanical stability of traditional structural materials when in contact with lead–bismuth eutectic (LBE). Addressing the degradation and failure mechanisms of structural and fuel cladding materials in the presence of LBE is of paramount importance for the advancement and application of LFR and ADS technologies. Among various candidate materials, ferrite/martensite (F/M) steel has been considered an ideal candidate for LBE-cooled reactor fuel cladding owing to its excellent mechanical properties, high-temperature mechanical performance, radiation resistance, and lower coefficient of thermal expansion. This study focuses on P91 F/M steel. Dynamic tests were performed for up to 3000 h in uncontrolled oxygen LBE at a relative flow velocity of 5 m·s?1 and temperatures of 350 ℃ and 450 ℃. The surface and cross-sectional corrosion morphologies of the alloy under different temperatures and exposure times were systematically analyzed by scanning electron microscopy. The composition and structural evolution of the oxide layer formed on P91 steel were summarized, and the mechanism of oxide layer spallation was proposed. In addition, electron backscatter diffraction was used to analyze the grain size, stress distribution, and proportion of large-angle grain boundaries in different impact angle regions between LBE and the samples, providing a detailed discussion of the erosion mechanism of the alloy in these regions. At 350 ℃, the oxide layer is a multilayer structure comprising a porous Fe3O4 layer, Fe-Cr spinel layer, and inner oxidation zone undergoing a dynamic equilibrium process of “formation–spallation–reformation”. At 450 ℃, the oxidation-corrosion phenomenon is severe, with LBE penetration observed in addition to oxidation. The corrosion characteristics on the sample surface vary significantly across different impact angle regions. The severity of surface damage is ranked as follows: 30° > 90° > ?90°. The oxide layer in the 30° angle region completely spalls, with LBE penetrating into the matrix. The 90° angle region shows spalling of the porous outer oxide layer, leaving only the inner oxide layer, with the inner matrix uneroded by LBE. The ?90° angle region maintains an intact oxide layer structure that is free from LBE erosion. In this work, the corrosion–erosion behaviors of P91 steel in high-velocity (5 m·s?1) LBE are studied, the formation and spallation mechanisms of the oxide scales are elucidated, and the erosion damage mechanism of the alloy are revealed, providing experimental data and references for the development of structural or cladding materials for China’s fourth-generation nuclear reactors and the study of their corrosion mechanisms in LBE.

     

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