The oxidation behavior of uranium treated by ultrasonic surface rolling process

被引:12
作者
Chen, Daoming [1 ,2 ]
Hu, Yin [1 ]
Li, Haibo [1 ]
Li, Fangfang [2 ]
Guo, Liang [2 ]
Pan, Qifa [1 ]
Ma, Ce [1 ]
Chen, Dong [2 ]
Liu, Jingyuan [2 ]
Liu, Kezhao [2 ]
机构
[1] Sci & Technol Surface Phys & Chem Lab, Mianyang 621908, Sichuan, Peoples R China
[2] China Acad Engn Phys, Inst Mat, Mianyang 621907, Sichuan, Peoples R China
基金
中国国家自然科学基金;
关键词
Ultrasonic surface rolling process; Uranium; Nano-grained layer; Oxidation behavior; MECHANICAL-PROPERTIES; CORROSION-RESISTANCE; KINETICS; STEEL; NANOCRYSTALLIZATION; MICROSTRUCTURE; EVOLUTION; OXYGEN; ALLOY; OXIDE;
D O I
10.1016/j.corsci.2021.109917
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The oxidation behavior of uranium treated by ultrasonic surface rolling process (USRP) was investigated. Optical microscopy (OM), transmission electron microscopy (TEM), x-ray diffraction (XRD), x-ray photo-electron spectroscopy (XPS), auger electron spectroscopy (AES), scanning electron microscopy (SEM), focused ion beam (FIB) and ultraviolet-visible reflectance spectroscopy were used to characterize the microstructure and oxidation behavior of uranium. The oxidation kinetics of USRP treated uranium with pure O2 at 343-388 K was subdivided into two different regimes: a linear-like stage and a parabolic-like stage. The calculated activation energies of USRP treated uranium were approximately 52.3kJ/mol and 75.1kJ/mol for linear and parabolic stages, respectively. The oxide thickness of untreated uranium generally followed a parabolic growth model and the activation energy was 61.4kJ/mol. After the USRP treatment, the nano-grained layer and the close-packed U (002) texture were formed, which promoted the formation of a passive and stable oxidation film on the surface. Meanwhile, the improved surface integrity and the residual compressive stress were obtained, which slowed down the rupture of the oxide layer. As a result, it was concluded that the enhancement of oxidation resistance after USRP treatment was attributed to the nano-grained microstructure, the U(002) texture, the residual compressive stress and the smooth surface.
引用
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页数:11
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共 38 条
[1]   X-RAY PHOTOELECTRON-SPECTROSCOPY OF SOME URANIUM OXIDE PHASES [J].
ALLEN, GC ;
CROFTS, JA ;
CURTIS, MT ;
TUCKER, PM ;
CHADWICK, D ;
HAMPSON, PJ .
JOURNAL OF THE CHEMICAL SOCIETY-DALTON TRANSACTIONS, 1974, (12) :1296-1301
[2]   SURFACE CHARACTERIZATION OF URANIUM METAL AND URANIUM-DIOXIDE USING X-RAY PHOTOELECTRON-SPECTROSCOPY [J].
ALLEN, GC ;
TRICKLE, IR ;
TUCKER, PM .
PHILOSOPHICAL MAGAZINE B-PHYSICS OF CONDENSED MATTER STATISTICAL MECHANICS ELECTRONIC OPTICAL AND MAGNETIC PROPERTIES, 1981, 43 (04) :689-703
[3]   Influence of Surface Roughness on Corrosion and Tribological Behavior of CP-Ti After Thermal Oxidation Treatment [J].
Arslan, E. ;
Totik, Y. ;
Demirci, E. ;
Alsaran, A. .
JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE, 2010, 19 (03) :428-433
[4]   Oxidation of a depleted uranium-5 wt% molybdenum (U-5Mo) alloy in UHV by AES and XPS [J].
Bacon, Simon R. ;
Brierley, Martin ;
Baker, Mark A. ;
Watts, John F. .
SURFACE AND INTERFACE ANALYSIS, 2019, 51 (08) :849-856
[5]   A review of the reaction rates of uranium corrosion in water [J].
Banos, A. ;
Scott, T. B. .
JOURNAL OF HAZARDOUS MATERIALS, 2020, 399
[6]   A review of uranium corrosion by hydrogen and the formation of uranium hydride [J].
Banos, A. ;
Harker, N. J. ;
Scott, T. B. .
CORROSION SCIENCE, 2018, 136 :129-147
[7]   The interaction of uranium metal with nitrogen oxides: The formation of an oxynitride surface layer [J].
Carley, Albert F. ;
Nevitt, Paul ;
Roussel, Paul .
JOURNAL OF ALLOYS AND COMPOUNDS, 2008, 448 (1-2) :355-362
[8]   The initial stage of uranium oxidation:: Mechanism of UO2 scale formation in the presence of a native lateral stress field [J].
Chernia, Z. ;
Ben-Eliyahu, Y. ;
Kimmel, G. ;
Braun, G. ;
Sariel, J. .
JOURNAL OF PHYSICAL CHEMISTRY B, 2006, 110 (46) :23041-23051
[9]   Ionic Diffusion Oxidation Model of Uranium [J].
Gharagozloo, Patricia E. ;
Kanouff, Michael P. .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2013, 96 (09) :2943-2949
[10]   OXIDATION OF URANIUM IN ARGON-25-PERCENT OXYGEN AT 190-610-DEGREES-C [J].
HAYWARD, PJ ;
EVANS, DG ;
TAYLOR, P ;
GEORGE, IM ;
DUCLOS, AM .
JOURNAL OF NUCLEAR MATERIALS, 1992, 187 (03) :215-222