Research Article
Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
Table 1
ICP-AES analysis of the SSF pellets before and after the immersion in the LKU molten salt.
| Category | Elements | As-fabricated (wt.%) | Salt-immersed (wt.%) |
| U | U | 83.6 | 84.5 | AE | Sr | 0.11 | 0.10 | Ba | 0.26 | 0.07 |
| RE | La | 0.16 | 0.08 | Ce | 0.31 | 0.20 | Pr | 0.15 | 0.08 | Nd | 0.53 | 0.28 | Sm | 0.10 | 0.03 | Eu | 0.02 | 0.02 | Gd | 0.04 | 0.02 | Y | 0.06 | 0.02 |
| Others | Zr | 0.63 | 0.60 | Rh | 0.02 | 0.02 | Mo | 0.02 | 0.01 |
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