Evaluation of Gamma Radiation Shielding for Nuclear Waste Shipping Casks

Year
1998
Author(s)
Y.Y. Liu - Argonne National Laboratory
R. D. Carlson - Energy Technology Division, Argonne National Laboratory
S. J. Primeau - Eagle Research Group, Inc., USA
Michael E. Wangler - U.S. Department of Energy
File Attachment
1179.PDF1.28 MB
Abstract
A method has been developed for evaluating ganuna radiation shielding of shipping casks that are used to transport nuclear waste with ill-defined radionuclide contents. 1be method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste, assuming that each radionuclide is unifonnly distributed in a volumetric source in the cask. For multiple radionuclide mixtures, a linear fraction rule is used to restrict the total amount of radionuclides such that the sum of the fractions does not exceed I. As long as the radionuclide limits and the linear fraction rule are folJowed, it can be shown that the regulatory dose rate requirements for a cask will be satisfied under normal conditions of transport and in a hypothetical accident during which the shielding thickness of the cask has been reduced by 40%.