Abstract
Exposure testing of Stainless Steel 316L was performed in LiCl-Li 2 O-Li solutions at 650 °C for periods of 500 and 1000 h to investigate the effect of metallic Li on corrosion of materials used to contain the LiCl-Li 2 O electrolyte for the electrolytic reduction of used nuclear fuel. Melt compositions studied consisted of LiCl containing 1 or 2 wt% Li 2 O and 0, 0.3, 0.6, or 1 wt% Li. Post exposure surface analysis was performed using scanning electron microscopy coupled with energy dispersive X-ray spectroscopy, Raman spectroscopy, X-ray photoelectron spectroscopy, and X-ray diffraction. Focused ion beam and mechanical cross sections of the samples and gravimetric analyses were performed to determine the time-averaged corrosion rate for each sample. Lithium metal induced attack rates were found to be as high as 2.91 mm/y. In the absence of solvated Li in the LiCl-Li 2 O system, LiCrO 2 , Li 2 CrO 4 , and NiFe x Cr 2-x O 4 were observed to be the primary corrosion products. When Li was present in the melt, the oxidized alloying elements were only detectable via X-ray photoelectron spectroscopy, and the surface was primarily comprised of bare metal.
| Original language | English |
|---|---|
| Pages (from-to) | 241-253 |
| Number of pages | 13 |
| Journal | Journal of Nuclear Materials |
| Volume | 517 |
| DOIs | |
| State | Published - Apr 15 2019 |
| Externally published | Yes |
Keywords
- Electroreduction
- High temperature
- Pyroprocessing
- SS316L
- XPS
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