Estimate of the Source Term for a Repository Surface Facility From the Routine Processing of Spent Fuel

by J. Mishima, Pacific Northwest Lab, United States,
K. M. Olson, Pacific Northwest Lab, United States,

Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1990


The potential for release of radioactive material from the proposed handling and processing of spent nuclear fuel in a surface facility for a geologic repository was evaluated. The potential sources evaluated were 1) the crud that can be spalled from the exterior surfaces of the spent fuel and hardware, 2) the contained radionuclides that can be released from cladding failure, and 3) the surface contamination that could be resuspended from the cell and equipment surfaces. The radionuclides in particulate forms are assumed to pass through the emission control system.

Subject Headings: Fuels | Nuclear power | Control systems | Radioactive wastes | Waste treatment | Spalling | Industrial wastes | Geology

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