Nuclear Engineering and Technology

  • 제56권5호
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  • Pages.1738-1746
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Europium-driven Alloy 709 corrosion in static FLiNaK molten salt at 700 ℃

  • Taiqi Yin (Nuclear Materials and Fuel Cycle Center, Department of Mechanical Engineering, Virginia Polytechnic Institute and State University) ;
  • Amanda Leong (Nuclear Materials and Fuel Cycle Center, Department of Mechanical Engineering, Virginia Polytechnic Institute and State University) ;
  • Jinsuo Zhang (Nuclear Materials and Fuel Cycle Center, Department of Mechanical Engineering, Virginia Polytechnic Institute and State University)
  • 투고 : 2023.03.09
  • 심사 : 2023.12.11
  • 발행 : 2024.05.25
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초록

The effect of europium-driven corrosion behavior of Alloy 709 in FLiNaK molten salt was investigated by static immersion tests at 700 ℃. It was found that the corrosion of Alloy 709 increased after the addition of EuF3, even though the standard reduction potential of Eu(III)/Eu(II) was negative than those of Fe(II)/Fe, Ni(II)/Ni and Cr (II)/Cr. The presence of Eu(III) led to deeper corrosion attack layers and more pits on the steel surface in comparison with corrosion in blank FLiNaK. However, the addition of Eu(III) seemed to have a role in reducing surface cracking that was explored in corrosion by blank FLiNaK, which depended on Eu(III) concentration.

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과제정보

Taiqi Yin gratefully acknowledges the financial support from China Scholarship Council, and the acceptance/support by the Department of Mechanical Engineering at Virginia Polytechnic Institute and State University, USA. The authors would like to acknowledge Qiufeng Yang and Weiqian Zhuo for discussion.

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