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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

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