REPROCESSING OF POWER REACTOR FUELS THIRTEENTH QUARTERLY PROGRESS REPORT, OCTOBER 1, 1960 TO JANUARY 1, 1961
Technical Report
·
OSTI ID:4009774
S>The corrosion of 304L stainless steel by boiling solutions of electrolytically dissolved Zircaloy-2 was found to be less than 3 mils per year(mpy). At 85 deg C the corrosion of 304L stainless steel by electrolytically dissolved stainless steel in nitric acid was about 10 mpy. Operation at 90 deg C did not decrease the dissolution rate of UO/sub 2/ appreciably below that at the boiling point. During the electrolytic disintegration of zirconium-uranium alloy, sludge was formed that contained uranium from both phases of the alloy. X- ray diffraction studies of the sludge indicated that the uranium was retained as (Zr-U)O/sub 2/. (auth)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
- NSA Number:
- NSA-15-018437
- OSTI ID:
- 4009774
- Report Number(s):
- DP-574
- Country of Publication:
- United States
- Language:
- English
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