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Title: Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects: report for October-December 1983

Technical Report ·
OSTI ID:6899523

Radionuclide solubility data and retardation parameters reported by the Basalt Waste Isolation Project (BWIP) and the experimental and calculational methodologies used by BWIP to develop those values were evaluated. The behavior of neptunium and technetium in basalt/synthetic groundwater systems was studied. Under oxic redox conditions, neptunium had a sorption ratio of 1.7 L/kg for McCoy Canyon basalt and synthetic groundwater GR-2, which is lower than the conservative best estimate value recommended by BWIP. Under anoxic test conditions, McCoy Canyon basalt showed little or no ability to remove technetium(VII) from synthetic groundwater GR-2 by sorption or precipitation. Several important concerns may make it impossible to assert that the addition of hydrazine to synthetic groundwaters is modeling the repository redox condition. These are: its reaction with any reducible solute is undefined; its dissociation to release hydroxide ions probably dominates the groundwater pH; it could react with bicarbonate to form the carbamate ion; it is corrosive t- polycarbonate or polypropylene test tubes; it may alter or disaggregate clay mineral structure; and uncertainty exists as to the solid phase or solution species formed by reaction with pertechnetate ion. Thus, BWIP data obtained in the presence of hydrazine may be nonconservative for use in assessment studies.

Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6899523
Report Number(s):
NUREG/CR-3851-Vol.1; ORNL/TM-9191/V1; ON: TI84013741
Country of Publication:
United States
Language:
English