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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| Online Access: |
Online Access |
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| Corporate Authors: | , |
| 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.
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| Subjects: |
| Summary: | 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 intended for use as preliminary source terms for calculating total system performance. The radionuclides specified for preliminary release-rate calculations are Tc-99, I-129, Cs-135, and Np-237 for ground-water pathways and C-14 for gaseous release. |
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| Item Description: | Published through the Information Bridge: DOE Scientific and Technical Information. 06/01/1990. "lbl--31069" "DE92009137" Lee, K.H.; Lee, W.W.L.; Pigford, T.H.; Apted, M.J.; ÒConnell, W.J.; Ueng, T.-S.; MacIntyre, A.T. |
| Physical Description: | 38 p. : digital, PDF file. |