Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects: Report for April 1986--September 1987

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During this report period, all experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. Batch sorption ratio determinations were conducted for strontium, cesium, uranium, and technetium onto samples of tuff using real and synthetic groundwater J-13. There were no significant differences in sorption ratios in experiments with real and synthetic groundwater. Columns were tested by determination of elution curves in J-13 containing tritium and technetium as the TcO{sub 4}/sup {minus}/ ion. For strontium and cesium, fairly good correlation between values of the sorption ratio obtained by the two methods was observed. Little technetium ... continued below

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Medium: P; Size: 65 p.

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Meyer, R.E.; Arnold, W.D.; Blencoe, J.G.; O`Kelley, G.D. & Land, J.F. July 1, 1988.

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Description

During this report period, all experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. Batch sorption ratio determinations were conducted for strontium, cesium, uranium, and technetium onto samples of tuff using real and synthetic groundwater J-13. There were no significant differences in sorption ratios in experiments with real and synthetic groundwater. Columns were tested by determination of elution curves in J-13 containing tritium and technetium as the TcO{sub 4}/sup {minus}/ ion. For strontium and cesium, fairly good correlation between values of the sorption ratio obtained by the two methods was observed. Little technetium sorption was observed with either method. The elution peaks obtained with neptunium and uranium were asymmetrical and the shapes were often complex, observations which suggest irreversibilities in the sorption reaction. Synthetic groundwater J-13 was slowly dripped onto a slab of tuff maintained at 95--100{degree}C, and the result was a thin encrustation of solids on the slab as the water evaporated. Fresh J-13 groundwater was then allowed to contact the encrustation in a vessel maintained at 90{degree}C. The principal result of the experiment was a significant loss of calcium and magnesium from the fresh J-13 groundwater. 13 refs. 25 figs., 9 tabs.

Physical Description

Medium: P; Size: 65 p.

Notes

NTIS, PC A04/MF A01 - GPO; OSTI as TI88015467

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  • Other Information: PBD: Jul 1988

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  • Other: TI88015467
  • Report No.: NUREG/CR--4708-Vol.2
  • Report No.: ORNL/TM--10147-Vol.2
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/60473 | External Link
  • Office of Scientific & Technical Information Report Number: 60473
  • Archival Resource Key: ark:/67531/metadc697390

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  • July 1, 1988

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  • Aug. 14, 2015, 8:43 a.m.

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  • Aug. 3, 2016, 1:47 p.m.

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Meyer, R.E.; Arnold, W.D.; Blencoe, J.G.; O`Kelley, G.D. & Land, J.F. Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects: Report for April 1986--September 1987, report, July 1, 1988; United States. (digital.library.unt.edu/ark:/67531/metadc697390/: accessed September 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.