Technical Basis for Eliminating Carbon-14 As A Reportable Radionuclide in DWPF Glass

PDF Version Also Available for Download.

Description

The Defense Waste Process Facility, DWPF, of Savannah River Site, SRS, is immobilizing the High Level Waste, HLW, sludges at SRS into a borosilicate glass for geologic disposal in a repository. In order for the glass to be acceptable to the repository, a set of acceptance specifications have been written. These are published as the ''Waste Acceptance Product Specifications, WAPS, for Vitrified High-Level Waste Forms.'' Specification 1.2 of the WAPS requires that, ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than ... continued below

Physical Description

vp.

Creation Information

NED, BIBLER December 1, 2004.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Author

Sponsor

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Description

The Defense Waste Process Facility, DWPF, of Savannah River Site, SRS, is immobilizing the High Level Waste, HLW, sludges at SRS into a borosilicate glass for geologic disposal in a repository. In order for the glass to be acceptable to the repository, a set of acceptance specifications have been written. These are published as the ''Waste Acceptance Product Specifications, WAPS, for Vitrified High-Level Waste Forms.'' Specification 1.2 of the WAPS requires that, ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115''. As part of the strategy developed to meet Specification 1.2, the DWPF elected to report for each waste type, all radionuclides with half-lives greater than 10 years that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. For the sludge batches processed thus far by the DWPF, either 26 or 27 radionuclides have been identified as reportable in the first three sludge batches. One of these radionuclides is carbon-14. This report presents results of an investigation to determine if carbon and thus the carbon-14 would survive DWPF processing and be reportable in DWPF glass. Based on a thorough literature review, a review of process knowledge, and the expected chemistry of carbon in the DWPF process, we conclude all chemical forms of carbon in SRS HLW are converted to gaseous oxides during DWPF processing. Thus carbon-14 would not be a reportable component of the final HLW glass.

Physical Description

vp.

Source

  • Other Information: PBD: 1 Dec 2004

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • Report No.: WSRC-TR-2004-00629
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/838802 | External Link
  • Office of Scientific & Technical Information Report Number: 838802
  • Archival Resource Key: ark:/67531/metadc785592

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • December 1, 2004

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

Description Last Updated

  • May 5, 2016, 2:50 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 2

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

NED, BIBLER. Technical Basis for Eliminating Carbon-14 As A Reportable Radionuclide in DWPF Glass, report, December 1, 2004; South Carolina. (digital.library.unt.edu/ark:/67531/metadc785592/: accessed October 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.