Description: This report describes an estimate of how much tritium will be held up in those parts of the 232-H process that will remain in the building after deactivation The anticipated state of this tritium is also discussed. This information will be used to assess the radiological status of the deactivated facility.
Date: January 7, 2003
Creator: Clark, E.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department