Poisitron annihilation study on corrosion-incudced defects in UNS N10003 alloy exposed to tellurium-containing FLiNaK salt

IF 3.3 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Journal of Nuclear Materials Pub Date : 2026-02-01 Epub Date: 2025-12-13 DOI:10.1016/j.jnucmat.2025.156377
Hongxia Xu , Bin Leng , Qi Liu , Wei Xu , Jiandang Liu , Bangjiao Ye , Hefei Huang , Xingtai Zhou , Run Ye
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引用次数: 0

Abstract

Positron annihilation spectroscopy reveals the effect of tellurium on the corrosion behavior of UNS N10003 in FLiNaK salts at 650°C. Te exposure increased mass loss 16-fold (0.48 vs 0.03 mg/cm²), with inductively coupled plasma optical emission spectrometry (ICP-OES) showing elevated Fe and Cr concentrations but depleted Te in the FLiNaK salts. X-ray diffraction (XRD) and scanning electron microscopy (SEM) identified Ni₃Te₂ precipitates at grain boundaries (GBs) and M6C carbide-matrix interfaces, which induce the τ₃ component in positron annihilation spectra due to void trapping. Coincidence Doppler broadening (CDB) confirmed defect proliferation via elevation of the S-parameter. Ni₃Te₂ precipitates failed to suppress Cr dissolution and accelerated GBs weakening, thereby promoting intergranular cracking or embrittlement.
unsn10003合金暴露于含碲的FLiNaK盐中腐蚀缺陷的泊电子湮没研究
正电子湮没光谱揭示了碲对UNS N10003在650℃下在FLiNaK盐中的腐蚀行为的影响。暴露使质量损失增加了16倍(0.48 vs 0.03 mg/cm²),电感耦合等离子体光学发射光谱(ICP-OES)显示,FLiNaK盐中的Fe和Cr浓度升高,但Te耗尽。x射线衍射(XRD)和扫描电镜(SEM)在晶界(GBs)和M6C碳化物-基体界面处发现Ni₃Te₂沉淀,由于空穴捕获导致正电子湮没谱中出现τ₃分量。重合多普勒增宽(CDB)通过s参数升高证实了缺陷增生。Ni₃Te₂的析出未能抑制Cr的溶解,反而加速了GBs的弱化,从而促进了晶间开裂或脆化。
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来源期刊
Journal of Nuclear Materials
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.
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