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The AAPG/Datapages Combined Publications Database
AAPG Special Volumes
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As of July 1, 1971, approximately 100 million kw of nuclear-power-plant capacity was in operation or under construction and/or contract. During the 1960s, an extensive research, development, and demonstration program was carried out on the treatment and disposal of all types of gaseous, liquid, and solid radioactive wastes. Geochemical research and extensive field exploration and demonstration studies have been carried out on several deep disposal systems for radioactive wastes, including the application of hydrofracturing techniques in bedded shale for low-heat-producing wastes and the use of bedded salt and crystalline bedrock for highly radioactive wastes.
The Atomic Energy Commission has adopted a regulatory policy which requires that all high-level liquid wastes from licensed irradiated-fuel-reprocessing plants must be solidified and shipped to a national repository on land owned and controlled by the federal government. A tentative selection of a site near Lyons, Kansas, has been made for an initial salt-mine repository for the demonstration of long-term storage for both solid high-level and long-lived alpha-contaminated wastes.
Because of a general requirement for adequate monitoring to assure the safe and effective operation of a deep-well injection system, this method has not been used generally for disposal of radioactive wastes. It appears that injection into deep permeable formations may be a practical solution for the disposal of large quantities of tritium-bearing wastes from water reactors and nuclear-fuel-reprocessing plants in the future. Additional research is also required on the potential deep disposal of noble gases such as krypton-85 from reactor and reprocessing-plant off-gas streams.
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