Abstract
A comparison of similarities and differences for processing UO2- and NpO2-based feed materials has been useful in planning for advanced processing methods and new requirements. Use of existing multistage solvent extraction equipment and shielded processing facilities at the ORNL REDC has enabled development, demonstration, and application of new and improved separations methods.
| Original language | English |
|---|---|
| Pages (from-to) | 195-196 |
| Number of pages | 2 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 114 |
| Issue number | 1 |
| State | Published - 2016 |
| Event | 2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016 - New Orleans, United States Duration: Jun 12 2016 → Jun 16 2016 |
Funding
Funding for this program is provided by the National Aeronautics and Space Administration through the U.S. Department of Energy, Office of Nuclear Energy.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | |
| National Aeronautics and Space Administration | |
| Office of Nuclear Energy |