Laboratory studies of radionuclide transport in fractured Climax granite
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, {sup 85}Sr and /sup 95m/Tc showed little or no retardation, whereas {sup 137}Cs 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 {sup 137}Cs than most natural fractures. Estimated fracture apertures from 18 to 60 {mu}m and hydraulic conductivities from 1.7 to 26 x 10{sup -3} m/s were calculated from the core measurements.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 59253
- Report Number(s):
- UCRL-53308; ON: DE83001709
- Resource Relation:
- Other Information: PBD: Jun 1982
- Country of Publication:
- United States
- Language:
- English
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54 ENVIRONMENTAL SCIENCES
GRANITES
RADIONUCLIDE MIGRATION
SORPTIVE PROPERTIES
STRONTIUM 85
ENVIRONMENTAL TRANSPORT
SORPTION
TECHNETIUM 95
CESIUM 137
GROUND WATER
NEVADA TEST SITE
FRACTURES
TRITIUM OXIDES
ISOMERIC NUCLEI
RADIOACTIVE WASTE DISPOSAL
UNDERGROUND DISPOSAL
WATER CHEMISTRY
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