Thermal corrosion behavior of Inconel 693, Hastelloy N and 310S in ceramic waste forming reactions

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-09-18 DOI:10.1016/j.jnucmat.2024.155416

Zongyao Ge , Shengheng Tan , Yingju Li , Liangjin Bao , Xiaohui Feng , Tianyu Liu , Yuansheng Yang

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Abstract

The thermal corrosion behavior of Inconel 693, Hastelloy N, and 310S was investigated in the reaction environment of ceramic waste forming reactions. Due to the difference in Cr content and the effect of chlorides, the high Cr Inconel 693 and 310S alloys exhibit selective corrosion by Cr, while the low Cr Hastelloy N exhibits uniform corrosion and the volatilization of MoO₃ caused high dimensional losses. The different behavior of the alloys in different corrosive environmental regions is also discussed. In the sintered product region, due to the encapsulation of the sintered product and the corrosion inhibiting role played by O²⁻, Hastelloy N alloy and 310S alloy experienced milder corrosion compared to alloy in the atmosphere region. And in the atmosphere region, the more abundant gas supply and the open environment caused Hastelloy N alloy and 310S alloy to experience more severe erosion. However, for Inconel 693 alloy, it formed a continuous spinel phase layer containing FeCr₂O₄ due to the higher partial pressure of O₂ in the atmosphere region, resulting in more slight corrosion compared to the sintered product region.

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铬镍铁合金 693、哈氏合金 N 和 310S 在陶瓷废料成型反应中的热腐蚀行为

研究了因科镍合金 693、哈氏合金 N 和 310S 在陶瓷废物成型反应环境中的热腐蚀行为。由于铬含量的不同和氯化物的影响，高铬 Inconel 693 和 310S 合金表现出铬的选择性腐蚀，而低铬 Hastelloy N 则表现出均匀腐蚀，MoO3 的挥发造成了较高的尺寸损失。此外，还讨论了合金在不同腐蚀环境区域的不同行为。在烧结产品区域，由于烧结产品的封装和 O2- 的缓蚀作用，哈氏合金 N 和 310S 的腐蚀比大气区域的合金要轻微。而在大气区，更充足的气体供应和开放的环境导致哈氏合金 N 和 310S 受到更严重的侵蚀。然而，对于 Inconel 693 合金而言，由于大气区域中的氧气分压较高，它形成了含有 FeCr2O4 的连续尖晶石相层，因此与烧结产品区域相比，腐蚀更为轻微。

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.