Preliminary calculations of release rates of Tc-99, I-129, and Np-237 from spent fuel in a potential repository in tuff

Preliminary calculations of release rates of Tc-99, I-129, and Np-237 from spent fuel in a potential repository in tuff [electronic resource]

This report presents preliminary calculations of time-dependent release rates of selected radionuclides from the engineered barrier system in a potential high-level waste repository in unsaturated tuff, representative of a potential repository at Yucca Mountain in southern Nevada. These results are...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Lawrence Berkeley Laboratory (Researcher), Lawrence Berkeley National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1990.
Subjects:
Porosity.
Time Dependence.
Tuff.
Iodine 129.
Rocks.
Solubility.
Spent Fuels.
Environmental Transport.
High-level Radioactive Wastes.
Radioactive Waste Disposal.
Neptunium 237.
Yucca Mountain Project.
Technetium 99.
Radionuclide Migration.
Yucca Mountain.
Nuclear Fuels.

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Call Number: E 1.99:lbl--31069
E 1.99:lbl--31069 Available

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