Open AccessDefense HLW Glass Degradation Model
Author(s) -
Denis M. Strachan
Publication year - 2004
Language(s) - English
Resource type - Reports
DOI - 10.2172/839531
Subject(s) - radioactive waste , vitrification , degradation (telecommunications) , dissolution , high level waste , radionuclide , waste management , environmental science , materials science , chemical engineering , engineering , nuclear physics , physics , telecommunications
The purpose of this report is to document the development of a model for calculating the release rate for radionuclides and other key elements from high-level radioactive waste (HLW) glasses under exposure conditions relevant to the performance of the repository. Several glass compositions are planned for the repository, some of which have yet to be identified (i.e., glasses from Hanford and Idaho National Engineering and Environmental Laboratory). The mechanism for glass dissolution is the same for these glasses and the glasses yet to be developed for the disposal of DOE wastes. All of these glasses will be of a quality consistent with the glasses used to develop this report