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Inconel 617和Incoloy 800H合金在高温堆环境中的腐蚀行为研究

Corrosion behavior of Inconel 617 and Incoloy 800H alloys in a high temperature reactor environment

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【作者】 郑伟; 何学东; 李昊翔; 杜斌; 银华强; 张璜; 马涛;

【Author】 ZHENG Wei;HE Xue-dong;LI Hao-xiang;DU Bin;YIN Hua-qiang;ZHANG Huang;MA Tao;Institute of Nuclear and New Energy Technology,Tsinghua University;

【机构】 清华大学核能与新能源技术研究院;

【摘要】 高温气冷堆一回路采用氦气作为冷却剂,其中的痕量杂质在高温下会对蒸汽发生器的合金材料造成腐蚀。Inconel 617和Incoloy 800H合金是高温堆蒸汽发生器的重要候选材料,非纯氦气对这类高温合金的腐蚀主要包括氧化、脱碳和渗碳。为了探索高温合金在非纯氦气中的腐蚀机理,本研究搭建了一套配气式高温腐蚀实验台架,并对两种合金在900~980℃的非纯氦气中开展了腐蚀实验。实验结果表明,Inconel 617的氧化层在高温下易被破坏并伴随脱碳,而Incoloy 800H能够保持连续的氧化层生成。本研究对Inconel 617氧化层破坏机理进行了分析,并建立了理论模型进行腐蚀温度预测。同时,本研究对两种合金的腐蚀现象进行了对比分析,提出了导致腐蚀差异的原因。

【Abstract】 Helium is used as the coolant in the primary circuit of high temperature gas cooled reactor(HTGR).The trace impurities in it will cause corrosion to the materials of the steam generator at high temperatures.Inconel 617 and Incoloy800 H are considered to be the candidates for the steam generators of HTGR.The corrosion behaviors in impure helium include oxidation,decarburization,and carburization.In order to explore the corrosion mechanism of superalloy in impure helium,a facility dedicated for investigating the high temperature corrosion has been developed in this study,and the corrosion experiments were carried out at 900~980℃.The experimental results show that the oxide layer of Inconel 617 would be destroyed easily and accompanied by decarburization at high temperatures, while the Incoloy 800 H could maintain the continuous formation of the oxide layer.In this study,the failure mechanism of the oxide layer of Inconel 617 was analyzed and a theoretical model was established to predict corrosion temperature.Meanwhile,the corrosion phenomena of these two alloys were compared and analyzed,and the reasons for the corrosion differences were put forward.

【关键词】 高温堆; 高温合金; 腐蚀; 氧化层;
【Key words】 High temperature reactor; Superalloy; Corrosion; Oxide layer;
【基金】 国家重点研发项目(2020YFB1901600);国家科技重大专项(ZX06901);模块化HTGR超临界发电技术合作项目(ZHJTJZYFGWD2020);清华大学实验室创新基金项目
  • 【会议录名称】 中国核科学技术进展报告(第八卷) 中国核学会2023年学术年会论文集 第3册 核材料 核化学与放射化学 锕系物理与化学
  • 【会议名称】中国核学会2023年学术年会
  • 【会议时间】2023-10-17
  • 【会议地点】中国陕西西安
  • 【分类号】TL424;TG178
  • 【主办单位】中国核学会
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