skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F

Abstract

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.

Authors:
Publication Date:
Research Org.:
SRS
Sponsoring Org.:
USDOE
OSTI Identifier:
899689
Report Number(s):
WSRC-STI-2007-00051
TRN: US0702103
DOE Contract Number:  
DE-AC09-96SR18500
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; CONTAMINATION; DEACTIVATION; DECAY; DIFFUSION; GROUTING; RETENTION; STAINLESS STEELS; TRANSPORT; TRITIUM; WASTE FORMS; WASTES

Citation Formats

Clark, E. CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F. United States: N. p., 2007. Web. doi:10.2172/899689.
Clark, E. CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F. United States. doi:10.2172/899689.
Clark, E. Fri . "CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F". United States. doi:10.2172/899689. https://www.osti.gov/servlets/purl/899689.
@article{osti_899689,
title = {CALCULATION OF TRITIUM RETENTION AND RELEASE FROM COMPONENTS IN GROUT- SEGMENT 6 METALLIC WASTE FROM DEMOLISHED BUILDING 232-F},
author = {Clark, E},
abstractNote = {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.},
doi = {10.2172/899689},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Feb 09 00:00:00 EST 2007},
month = {Fri Feb 09 00:00:00 EST 2007}
}

Technical Report:

Save / Share: