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U.S. Department of Energy
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Dilute chemical decontamination program. Quarterly report 5, October 1-December 31, 1978

Technical Report ·
OSTI ID:6405071

The nominal concentrations for oxalic acid and citric acid were selected to be 0.01 and 0.005 M, respectively; the process conditions were selected to be pH3 and 90/sup 0/C with a controlled dissolved oxygen concentration. Additions of acridine, EDTA, and HEDTA with rapid regeneration were not successful in preventing the formation of ferrous-oxalate films on carbon steel surfaces. Control of the dissolved oxygen at an intermediate level prevents ferrous-oxalate precipitation but allows for the highest dissolution rate of fuel deposits. Six mini-loop tests indicated that no measurable quantities of ferrous oxalate will be left on steel surfaces at the end of a decontamination .20 to 50% of the Co-60 in the ferrous-oxalate films will be released during the purification process; however, the resulting iron oxide film will retain some of the Co-60. The data from the Vallecitos Nuclear Center (VNC) test loop run conducted with 0.02 M oxalic acid were analyzed. The Co-60 concentrations in solution were calculated for the mini-loop runs and the VNC test loop runs using the modified regeneration equation and were in agreement with measurement. A corrosion loop test was conducted to evaluate the effects of 0.02 M oxalic acid on 10 alloys or metallurgical conditions. Corrosion rates were acceptably low.

Research Organization:
General Electric Co., San Jose, CA (USA). Nuclear Engineering Div.
DOE Contract Number:
AC02-76ET34203
OSTI ID:
6405071
Report Number(s):
DOE/ET/34203-41; NEDC-12705-5; ON: DE81025690
Country of Publication:
United States
Language:
English

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