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U.S. Department of Energy
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Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects. Report for January-March 1984

Technical Report ·
OSTI ID:6227055
Geochemical information relevant to the retention of radionuclides by Department of Energy (DOE) candidate high-level waste repositories is being investigated by Oak Ridge National Laboratory (ORNL) for the Nuclear regulatory Commission (NRC). The project has evaluated values that have been reported by the Basalt Waste Isolation Project (BWIP) and the methodologies used to develop those values. Neptunium(V) sorption was dependent upon the basalt flow used in the test. Increasing the test temperature from 24 to 60/sup 0/C increased the neptunium sorption ratio. Hydrazine did not reduce neptunium(V) to neptunium(IV) in solution. The Amicon filters used to separate the basalt and groundwater after contact have been shown to adsorb a low but significant fraction of the neptunium(V) in solution. Technetium(VII) removal by basalt from groundwater solutions was shown to be independent of the contact methodology but was quite sensitive to the solution composition. Sorption of uranium(VI) by basalt has yielded sorption ratio values higher than those reported by BWIP. Column chromatographic experiments have confirmed the technetium(VII) sorption ratio of approx. 0 L/kg. The McCoy Canyon basalt used in this experimental work was mineralogically characterized. Six phases were identified: plagioclase, mesostasis, pyroxene, magnetite, apatite, and pyrite. Geochemical modeling with PHREEQE and MINTEQ checked the calculated solubilities of 16 radionuclides reported by BWIP; the agreement was generally excellent.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6227055
Report Number(s):
NUREG/CR-3851-Vol.2; ORNL/TM-9191-Vol.2; ON: TI85001477
Country of Publication:
United States
Language:
English