Published 1983
| Version v1
Book
Immobilization of acid digestion residue
Description
Acid digestion treatment of nuclear waste is similar to incineration processes and results in the bulk of the waste being reduced in volume and weight to some residual solids termed ''residue.'' The residue is composed of various dispersible solid materials and typically contains the resultant radioactivity from the waste. This report describes the immobilization of the residue in portland cement, borosilicate glass, and some other waste forms. Diagrams showing the cement and glass vitrification parameters are included in the report as well as process steps and candidate waste product forms. Cement immobilization is simplest and probably least expensive; glass vitrification exhibits the best overall volume reduction ratio
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Waste management '83. Vol. 1
- Journal Page Range
- p. 331-340.
Conference
- Title
- Waste management conference.
- Dates
- 27 Feb - 3 Mar 1983.
- Place
- Tucson, AZ (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17052098
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOROSILICATE GLASS; CEMENTS; COMPARATIVE EVALUATIONS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; SOLIDIFICATION; VITRIFICATION; WASTE FORMS
- Descriptors DEC
- BUILDING MATERIALS; EVALUATION; GLASS; MANAGEMENT; MATERIALS; RADIOACTIVE MATERIALS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES