Laboratory studies of radionuclide transport in fractured Climax granite [electronic resource].
- Livermore, Calif : Lawrence Livermore National Laboratory, 1982.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 73 pages : digital, PDF file
- Additional Creators:
- Lawrence Livermore National Laboratory
United States. Department of Energy. Office of Scientific and Technical Information
- This report documents our laboratory studies of radionuclide transport in fractured granite cores. To simulate natural conditions, our laboratory studies used naturally fractured cores and natural ground water from the Climax Granite Stock at the Nevada Test Site. For comparison, additional tests used artificially fractured granite cores or distilled water. Relative to the flow of tritiated water, ⁸⁵Sr and /sup 95m/Tc showed little or no retardation, whereas ¹³⁷Cs was retarded. After the transport runs the cores retained varying amounts of the injected radionuclides along the fracture. Autoradiography revealed some correlation between sorption and the fracture fill material. Strontium and cesium retention increased when the change was made from natural ground water to distilled water. Artificial fractures retained less ¹³⁷Cs than most natural fractures. Estimated fracture apertures from 18 to 60 μm and hydraulic conductivities from 1.7 to 26 x 10⁻³ m/s were calculated from the core measurements.
- Published through SciTech Connect.
Failor, R.; Raber, E.; Isherwood, D.; Vandergraaf, T.
- Funding Information:
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