Preliminary Calculations of Release Rates from Spent Fuel in a Tuff Repository

by M. J. Apted, Battelle, Pacific Northwest Lab, Richland, United States,
T. H. Pigford, Battelle, Pacific Northwest Lab, Richland, United States,
W. W. -L. Lee, Battelle, Pacific Northwest Lab, Richland, United States,
W. J. O'Connell, Battelle, Pacific Northwest Lab, Richland, United States,
K. H. Lee, Battelle, Pacific Northwest Lab, Richland, United States,
A. T. MacIntyre, Battelle, Pacific Northwest Lab, Richland, United States,
T. -S. Ueng, Battelle, Pacific Northwest Lab, Richland, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1991

Abstract: Time-dependent release rates of Tc-99, I-129, Cs-135, and Np-237 have been calculated for wet-drip and moist-continuous release modes from the engineered barrier system of a potential nuclear waste repository in unsaturated tuff. We describe the modes of water contact and of release of dissolved radionuclides to the surrounding intact rock, and the corresponding calculational models. We list the parameter values adopted, and then present numerical results, conclusions, and recommendations.

Subject Headings: Fuels | Radioactive wastes | Nuclear power | Time dependence | Moisture | Hydrologic models | Radioactive materials | Rocks

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