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Method of calculating test leakage rate for a spent fuel cask (open access)

Method of calculating test leakage rate for a spent fuel cask

This report presents a method for calculating containment test leakage rates of radionuclides from an example spent fuel cask. Three releasable radioactive sources are considered: residual contamination in the cask cavity, crud on the fuel elements, and the radionuclides within the fuel rods. The ANSI N14.5 standard is used to calculate the test leakage rates from the maximum permissible releases determined from 10 CFR 71 containment requirements. 6 refs., 2 tabs.
Date: June 13, 1990
Creator: Fischer, L. E.
System: The UNT Digital Library