ULTRASONIC LEACHING OF URANIA-IMPREGNATED GRAPHITE FUELS
The proposed use of unclad, urania-impregnated graphite fuel elements in experimental and power reactors raised the question of how best to reprocess the elements after irradiation. A grind-leach process using boiling nitric acid was previously suggested as alternate to earlier combustion techniques. Besides requiring pre-grinding of the elements the process did not leave a residue sufficiently low in radioactivity when the elements contained initially less than 3 wt% uranium. Application of ultrasonic vibratory energy tc the graphite during this process increased leaching rate and completeness tc such an extent that the practical process limit of 3% uranium is no longer a problem. The ultrasonic studies were carried out with non-irradiated specimen plates and ground pebble specimens. The plates apparently can be leached in practical time span to such a low level of radioactivity that disposal of the graphite residues is simplified. Furthermore it appears that the pre-grinding of the spent elements can be eliminated. Direct activation of the intact fuel plate specimens resulted in leaching efficiency at least as good as with ground specimens. (auth)
- Research Organization:
- Aeroprojects, Inc., West Chester, Penna.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(30-1)-1836
- NSA Number:
- NSA-15-024903
- OSTI ID:
- 4022354
- Report Number(s):
- NYO-9581
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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