Electrochemical Activity Measurements of UCl3 in Molten NaCl-MgCl2-UCl3

被引:0
作者
Yankey, Jacob [1 ]
Monreal, Marisa [2 ]
Jackson, Matt [2 ]
Simpson, Michael [1 ]
机构
[1] Univ Utah, Mat Sci & Engn Dept, 122 S Cent Campus Dr 304, Salt Lake City, UT 84112 USA
[2] Los Alamos Natl Lab, POB 1663, Los Alamos, NM 87545 USA
来源
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE | 2024年 / 10卷 / 03期
关键词
high-temperature electrochemistry; molten salt chemistry; MSR; reactor fuel candidate; chloride salt activity;
D O I
10.1115/1.4064598
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Open circuit potential (OCP) measurements were made to determine uranium chloride (UClx) species activity in NaCl-MgCl2, which is a candidate salt for use in a molten salt reactor fuel. The operating temperature ranged from 500 to 650( degrees)C, and the measurement system used a U-Zr working electrode (WE) and Ag/AgCl reference electrode (RE). The activity was calculated to range from 2.52x10(-6) to 2.99x10(-8) (with uncertainties of +/- 1.0x10(-7) and +/- 1.1x10(-9), respectively), dependent upon the temperature and concentration of UCl3 (ranging from 0.25 to 11.55 wt.%). Fit of the OCP data to the Nernst equation resulted in values of 3.1 to 4.8 electrons transferred per U atom. This indicates the possibility for codeposition of Mg2+ and U3+ under certain conditions. Scanning electron microscopy, energy-dispersive X-ray spectroscopy, and X-ray photo-electron spectroscopy analyses of cathodic deposits confirm the presence of metallic magnesium.
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页数:8
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