Evaluation of gamma radiation shielding for nuclear waste shipping casks
- Argonne National Lab., IL (United States). Energy Technology Div.
- Eagle Research Group, Inc., Germantown, MD (United States)
- Dept. of Energy, Germantown, MD (United States). Office of Transportation, Emergency Management and Analytical Services
A method has been developed for evaluating gamma radiation shielding of shipping casks that are used to transport nuclear waste with ill-defined radionuclide contents. The method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste, assuming that each radionuclide is uniformly 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 1. As long as the radionuclide limits and the linear fraction rule are followed, 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%.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 645503
- Report Number(s):
- ANL/ET/CP-94812; CONF-980507-; ON: DE98050530; TRN: 98:009932
- Resource Relation:
- Conference: PATRAM `98: 12. international conference on packaging and transportation of radioactive material, Paris (France), 10-15 May 1998; Other Information: PBD: May 1998
- Country of Publication:
- United States
- Language:
- English
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