Optimization of the factors that accelerate leaching [electronic resource]
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...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of Nuclear Energy, Science, and Technology ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1989.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Optimization of the factors that accelerate leaching |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Office of Nuclear Energy, Science, and Technology ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1989. | ||
| 300 | |a Pages: (138 p) : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 03/01/1989. | ||
| 500 | |a "bnl-52204" | ||
| 500 | |a "DE90000886" | ||
| 500 | |a Colombo, P.; Heiser, J.H. III; Franz, E.M.; Fuhrmann, M.; Pietrzak, R.F. | ||
| 520 | 3 | |a 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. | |
| 536 | |b AC02-76CH00016. | ||
| 650 | 7 | |a Beta Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Days Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Mathematical Models. |2 local. | |
| 650 | 7 | |a Alkaline Earth Isotopes. |2 local. | |
| 650 | 7 | |a Separation Processes. |2 local. | |
| 650 | 7 | |a Beta-minus Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Cobalt Isotopes. |2 local. | |
| 650 | 7 | |a Years Living Radioisot. |2 local. | |
| 650 | 7 | |a Low-level Radioactive Wastes. |2 local. | |
| 650 | 7 | |a Building Materials. |2 local. | |
| 650 | 7 | |a Wastes. |2 local. | |
| 650 | 7 | |a Cesium 137. |2 local. | |
| 650 | 7 | |a Electron Capture Radioisotopes. |2 local. | |
| 650 | 7 | |a Even-odd Nuclei. |2 local. | |
| 650 | 7 | |a Isotopes. |2 local. | |
| 650 | 7 | |a Waste Disposal. |2 local. | |
| 650 | 7 | |a Environmental Impacts. |2 local. | |
| 650 | 7 | |a Cobalt 60. |2 local. | |
| 650 | 7 | |a Cements. |2 local. | |
| 650 | 7 | |a Management. |2 local. | |
| 650 | 7 | |a Intermediate Mass Nuclei. |2 local. | |
| 650 | 7 | |a Materials. |2 local. | |
| 650 | 7 | |a Strontium 85. |2 local. | |
| 650 | 7 | |a Isomeric Transition Isotopes. |2 local. | |
| 650 | 7 | |a Odd-even Nuclei. |2 local. | |
| 650 | 7 | |a Alkali Metal Isotopes. |2 local. | |
| 650 | 7 | |a Odd-odd Nuclei. |2 local. | |
| 650 | 7 | |a Solidification. |2 local. | |
| 650 | 7 | |a Cesium Isotopes. |2 local. | |
| 650 | 7 | |a Minutes Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Radioactive Wastes. |2 local. | |
| 650 | 7 | |a Strontium Isotopes. |2 local. | |
| 650 | 7 | |a Ground Disposal. |2 local. | |
| 650 | 7 | |a Waste Management. |2 local. | |
| 650 | 7 | |a Cobalt 57. |2 local. | |
| 650 | 7 | |a Leaching. |2 local. | |
| 650 | 7 | |a Dissolution. |2 local. | |
| 650 | 7 | |a Internal Conversion Radioisotopes. |2 local. | |
| 650 | 7 | |a Waste Forms. |2 local. | |
| 650 | 7 | |a Nuclei. |2 local. | |
| 650 | 7 | |a Radioactive Materials. |2 local. | |
| 650 | 7 | |a Phase Transformations. |2 local. | |
| 650 | 7 | |a Years Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Radioisotopes. |2 local. | |
| 650 | 7 | |a Liquid Wastes. |2 local. | |
| 650 | 7 | |a Hours Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities. |2 edbsc. | |
| 710 | 2 | |a Brookhaven National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Office of Nuclear Energy, Science, and Technology. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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