Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin
Description
When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. An organic ion exchange resin is used. This resin was then mixed with sludge … continued below
Physical Description
16 pages
Creation Information
Bibler, N. E.; Bibler, J. P.; Andrews, M. K. & Jantzen, Carol M. January 1, 1991.
Context
This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 60 times. More information about this article can be viewed below.
Who
People and organizations associated with either the creation of this article or its content.
Sponsor
- United States. Department of Energy. DOE; USDOE, Washington, DC (United States)
Publisher
-
Westinghouse Savannah River Company
Publisher Info: Westinghouse Savannah River Co., Aiken, SC (United States)Place of Publication: Aiken, South Carolina
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 article. Follow the links below to find similar items on the Digital Library.
Description
When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. An organic ion exchange resin is used. This resin was then mixed with sludge andfrit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. Some of these are discussed in the paper. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. The redox state of the glass is lowered by the presence of the resin in the feed, but the glass is still suitable as a canistered wasteform for radioactive waste glass.
Physical Description
16 pages
Notes
OSTI; NTIS; INIS; GPO Dep.
Subjects
Keywords
- Alkali Metal Isotopes
- Beta Decay Radioisotopes
- Beta-Minus Decay Radioisotopes
- Borosilicate Glass
- Cesium 137
- Cesium Isotopes
- Chemical Analysis
- Chemical Reactions
- Decomposition
- Glass
- High-Level Radioactive Wastes
- Hydrolysis
- Inorganic Ion Exchangers
- Intermediate Mass Nuclei
- Ion Exchange
- Ion Exchange Materials
- Isotopes
- Lysis
- Management
- Materials
- Melting
- Minerals
- National Organizations
- Nuclei
- Odd-Even Nuclei
- Organic Compounds
- Ph Value
- Phase Transformations
- Processing
- Radioactive Materials
- Radioactive Waste Management
- Radioactive Waste Processing
- Radioactive Wastes
- Radioisotopes
- Redox Reactions
- Reliability
- Savannah River Plant
- Silicate Minerals
- Sludges
- Solvolysis
- Us Aec
- Us Doe
- Us Erda
- Us Organizations
- Vitrification
- Waste Management
- Waste Processing
- Wastes
- Years Living Radioisotopes 052001* -- Nuclear Fuels-- Waste Processing
- Zeolites
STI Subject Categories
Source
- 16. Material Research Society international symposium on the scientific basis for nuclear waste management fall meeting, Boston, MA (United States), 30 Nov - 5 Dec 1992
Language
Item Type
Identifier
Unique identifying numbers for this article in the Digital Library or other systems.
- Other: DE93006873
- Report No.: WSRC-MS-91-465
- Report No.: CONF-921101--92
- Grant Number: AC09-89SR18035
- Office of Scientific & Technical Information Report Number: 6668618
- Archival Resource Key: ark:/67531/metadc1185361
Collections
This article 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.
Digital Files
When
Dates and time periods associated with this article.
Creation Date
- January 1, 1991
Added to The UNT Digital Library
- July 3, 2018, 8:14 a.m.
Description Last Updated
- Oct. 22, 2019, 11:25 a.m.
Usage Statistics
When was this article last used?
Interact With This Article
Here are some suggestions for what to do next.
Start Reading
Citations, Rights, Re-Use
International Image Interoperability Framework
We support the IIIF Presentation API
Print / Share
Links for Robots
Helpful links in machine-readable formats.
Archival Resource Key (ARK)
- ERC Record: /ark:/67531/metadc1185361/?
- Persistence Statement: /ark:/67531/metadc1185361/??
International Image Interoperability Framework (IIIF)
- IIIF Manifest: /ark:/67531/metadc1185361/manifest/
Metadata Formats
- UNTL Format: /ark:/67531/metadc1185361/metadata.untl.xml
- DC RDF: /ark:/67531/metadc1185361/metadata.dc.rdf
- DC XML: /ark:/67531/metadc1185361/metadata.dc.xml
- OAI_DC: /oai/?verb=GetRecord&metadataPrefix=oai_dc&identifier=info:ark/67531/metadc1185361
- METS: /ark:/67531/metadc1185361/metadata.mets.xml
- OpenSearch Document: /ark:/67531/metadc1185361/opensearch.xml
Images
- Thumbnail: /ark:/67531/metadc1185361/thumbnail/
- Small Image: /ark:/67531/metadc1185361/small/
URLs
- In-text: /ark:/67531/metadc1185361/urls.txt
Stats
- Usage Stats: /stats/stats.json?ark=ark:/67531/metadc1185361
Bibler, N. E.; Bibler, J. P.; Andrews, M. K. & Jantzen, Carol M. Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin, article, January 1, 1991; Aiken, South Carolina. (https://digital.library.unt.edu/ark:/67531/metadc1185361/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.