期刊
SOLVENT EXTRACTION AND ION EXCHANGE
卷 29, 期 1, 页码 1-48出版社
TAYLOR & FRANCIS INC
DOI: 10.1080/07366299.2011.539134
关键词
Pretreatment; radioactive waste; cross-flow filter; rotary microfilter; cesium ion exchange; cesium solvent extraction; crystalline silicotitanate; monosodium titanate
资金
- U.S. Department of Energy, Office of Environmental Management
- U.S. Department of Energy [DE-AC05-76RL01830, DE-AC09-08SR22470]
The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste generated during the production of nuclear weapons in the United States. The general strategy for treating the radioactive tank waste consists of pretreating the wastes by separating them into high-level and low-activity fractions. The high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for on-site. This paper reviews recent developments in the application of pretreatment technologies to the processing of the DOE radioactive tank wastes.
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