期刊
SEPARATION SCIENCE AND TECHNOLOGY
卷 46, 期 7, 页码 1087-1097出版社
TAYLOR & FRANCIS INC
DOI: 10.1080/01496395.2011.554951
关键词
alkaline waste; iodometric titration; ion exchange; neptunium; peroxotitanate; plutonium; uranium
资金
- U.S. Department of Energy through the Office of Waste Processing in the Office of Environmental Management
High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site requires pretreatment to remove 134,137Cs, 90Sr, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. An inorganic sorbent, monosodium titanate, is currently used to remove 90Sr and alpha-emitting radionuclides, while a caustic-side solvent extraction process is used for removing 134,137Cs. A new peroxotitanate material has recently been developed and has shown increased removal kinetics and capacity for 90Sr and alpha-emitting radionuclides compared to the current baseline material. This article describes recent results focused on further characterization of this material.
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