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Behavior of technetium in nuclear waste vitrification processes
1Vitreous State Laboratory, The Catholic University of America, 620 Michigan Avenue, NE, Washington, DC 20064 USA.
Journal of Radioanalytical and Nuclear Chemistry
|July 31, 2015
Summary
Technetium retention during waste vitrification averaged 35% in single-pass tests. Recycling off-gas treatment fluids significantly improved technetium capture, minimizing losses from the waste immobilization process.
Area of Science:
- Nuclear Chemistry
- Materials Science
- Environmental Engineering
Background:
- Nuclear waste vitrification immobilizes radioactive waste in borosilicate glass.
- Technetium (Tc) is a volatile radionuclide of concern during waste vitrification.
- Low activity waste from Hanford tanks requires immobilization.
Purpose of the Study:
- Investigate technetium behavior during waste vitrification.
- Quantify technetium incorporation into glass melt.
- Determine technetium partitioning to off-gas and capture efficiency.
Main Methods:
- Conducted nearly 100 tests using prototypical melters and off-gas system components.
- Utilized simulants of Hanford low activity waste spiked with 99mTc and Rhenium (Re).
- Evaluated technetium retention and partitioning under various conditions.
Main Results:
- Single-pass technetium retention averaged approximately 35%.
- Recycling off-gas treatment fluids significantly enhanced technetium capture efficiency.
- The fraction of technetium escaping the recycle loop was minimal.
Conclusions:
- Waste vitrification processes require careful management of technetium volatility.
- Off-gas recycling is crucial for maximizing technetium capture during immobilization.
- Effective technetium capture is achievable with optimized off-gas treatment.
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