Inconel 617在VHTR非纯氦环境中的腐蚀行为和力学性能的初步研究

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-08-08 DOI:10.1115/icone29-88943
B. Du, Huaqiang Yin, Tengyu Ma, Haoxiang Li, Weizhen Zheng, Xuedong He
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引用次数: 0

摘要

超高温堆(VHTR)一般采用氦气作为冷却剂,但在施工、运行和维护过程中,主冷却剂中不可避免地混入少量杂质气体。在高温下,这些杂质气体会与中间换热器的合金材料发生腐蚀,导致高温合金材料性能下降。本文主要研究了高温反应器中间换热器候选材料Inconel 617在950℃非纯氦中时效50 h后的组织和力学性能变化。通过称重、扫描电镜和x射线能谱分析表征了合金的显微组织。腐蚀后,合金表面形成Cr氧化层,氧化层下方出现Al内氧化。力学试验结果表明,Inconel 617的强度和塑性明显下降,这与晶间氧化物和碳化物的存在有关。合金的断裂形貌以脆性断裂为主。
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Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR
Helium is generally used as coolant in Very-High-Temperature Reactor (VHTR), but a small amount of impurity gas will inevitably be mixed in the primary coolant during construction, operation and maintenance. At high temperature, these impurity gases will corrode with the alloy materials of the intermediate heat exchanger, resulting in the decline of the properties of the superalloy materials. This paper mainly studied the changes of microstructure and mechanical properties of Inconel 617, a candidate material for high temperature reactor intermediate heat exchanger, after aging for 50 hours in impure helium at 950 °C. The microstructure of the alloy was characterized by weighing, scanning electron microscope and energy dispersive X-ray spectroscopy. After corrosion, Cr oxide layer was formed on the alloy surface, and Al internal oxidation appeared below the oxide layer. The mechanical test results showed that the strength and plasticity of Inconel 617 decreased significantly, which was related to the intergranular oxides and carbides. The fracture morphology of the alloy is mainly brittle fracture.
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CiteScore
0.80
自引率
25.00%
发文量
35
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