Optimization of the factors that accelerate leaching
Description
The prediction of long-term leachability of low-level radioactive waste forms is an essential element of disposal-site performance assessment. This report describes experiments and modeling techniques used to develop an accelerated leach test that meets this need. The acceleration in leaching rates caused by the combinations of two or more factors were experimentally determined. These factors were identified earlier as being able to individually accelerate leaching. They are: elevated temperature, the size of the waste form, the ratio of the volume of leachant to the surface area of the waste form, and the frequency of replacement of the leachant. The solidification agents employed were ones that are currently used to treat low-level radioactive wastes, namely portland type I cement, bitumen, and vinyl ester-styrene. The simulated wastes, sodium sulfate, sodium tetraborate, and incinerator ash, are simplified representatives of typical low-level waste streams. Experiments determined the leaching behavior of the radionuclides of cesium (Cs-137), strontium (Sr-85), and cobalt (Co-60 or Co-57) from several different formulations of solidification agents and waste types. Leaching results were based upon radiochemical and elemental analyses of aliquots of the leachate, and on its total alkalinity and pH at various times during the experiment (up to 120 days). Solid phase analyses were carried out by Scanning/Electron Microscopy and Energy Dispersive Spectroscopy on the waste forms before and after some leaching experiments. 43 refs., 96 figs., 16 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A07/MF A01 as DE90000886; OSTI; INIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 138 p.
- Report number
- BNL--52204
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21015347
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- CEMENTS; CESIUM 137; COBALT 57; COBALT 60; ENVIRONMENTAL IMPACTS; GROUND DISPOSAL; LEACHING; LIQUID WASTES; LOW-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; SOLIDIFICATION; STRONTIUM 85; WASTE FORMS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BUILDING MATERIALS; CESIUM ISOTOPES; COBALT ISOTOPES; DAYS LIVING RADIOISOTOPES; DISSOLUTION; ELECTRON CAPTURE RADIOISOTOPES; EVEN-ODD NUCLEI; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SEPARATION PROCESSES; STRONTIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016