Abstract
Sr-90 is utilized as a raw material in various fields such as nuclear batteries, medical applications, and industrial use as a beta particle source. Therefore, high-purity Sr-90 is required to increase the thermal efficiency of nuclear battery operation or to prevent side effects on the human body during its use in medical therapy. Sr-90 is present in spent nuclear fuel and can be separated via reactive distillation through a pyrochemical process developed at the Korea Atomic Energy Research Institute, where Ba is obtained simultaneously via co-precipitation owing to its chemical similarity. In addition, Sr-90 decays into Zr-90 during the storage period after separation. Therefore, Ba and Zr-90 should be separated to obtain high-purity Sr-90 nuclides. In the present study, a separation and purification process is developed for the recovery of Sr-90 from a waste mixture containing Sr-90, Ba, and Zr-90. To separate Ba and Zr-90, the chromate precipitation reaction is modified via pH control, which can enhance the precipitation efficiency of Ba and prevent the co-precipitation of Sr owing to the excess amount of precipitants. A systematic study is conducted to optimize Sr-90 separation and purification processes, where a high yield of 84.3% is obtained, and a high purity exceeding 99.9% is maintained.
Original language | English |
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Pages (from-to) | 275-281 |
Number of pages | 7 |
Journal | Journal of Radioanalytical and Nuclear Chemistry |
Volume | 331 |
Issue number | 1 |
DOIs | |
State | Published - Jan 2022 |
Keywords
- Heat source
- Nuclide separation
- Precipitation
- Purification
- Spent nuclear fuel recycling
- Strontium-90