Actions for CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F [electronic resource].

Email RIS file
Bookmark
Report an Issue

CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 2007.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
United States. Department of Energy. Savannah River Site, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access
Free-to-read Unrestricted online access
Summary
The amount of tritium remaining within and the release rate out of stainless steel process waste from the 232-F Tritium Facility at SRS is calculated as a function of time using the historical exposure of pipe during operation of the facility (1955-1958) and its subsequent deactivation and lay-up. The solution and diffusion of tritium in the wall is the mechanism that governs both the tritium contamination of the pipe during operation and its gradual release after deactivation, including radioactive decay while in the metal. This analysis applies to Segment 6 of the so-called Components in Grout waste form. Results of these calculations will be used in the Groundwater Transport assessment, part of the analysis of the Components in Grout.
Report Numbers
E 1.99:wsrc-sti-2007-00051
wsrc-sti-2007-00051
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
02/09/2007.
"wsrc-sti-2007-00051"
Clark, E.
Funding Information
DE-AC09-96SR18500
View MARC record | catkey: 14408153