4.1 Article

RATES OF EXCHANGE OF Cs+ AND Sr2+ FOR POORLY CRYSTALLINE SODIUM TITANIUM SILICATE (CST) IN NUCLEAR WASTE SYSTEMS

期刊

SOLVENT EXTRACTION AND ION EXCHANGE
卷 30, 期 3, 页码 229-243

出版社

TAYLOR & FRANCIS INC
DOI: 10.1080/07366299.2011.639256

关键词

Radioactive waste; ion exchange; CST and Nb-CST; sodium titanium silicate; improved kinetics of exchange

资金

  1. U.S. Department of Energy, Office of Basic Energy Sciences
  2. National Science Foundation [DMR-0652166]
  3. Heavy Element Chemistry Program [DE-FG02-03ER15420]
  4. U.S. Department of Energy (DOE) [DE-FG02-03ER15420] Funding Source: U.S. Department of Energy (DOE)

向作者/读者索取更多资源

The compound sodium titanium silicate, popularly known as CST, is highly selective for Cs+. It was synthesized for the purpose of removing Cs-137 from basic nuclear waste systems. This compound has a tunnel structure in which the Cs+ ion just fits but diffusion through the tunnels is relatively slow. CST loses its ability to sequester Cs+ in the strongly basic nuclear waste solutions. However, replacement of titanium with 25 mol% of niobium increases the selectivity to a satisfactory level. It has been found that producing a less crystalline form of Nb-CST greatly improves the rate of Cs+ removal. Additionally, the non-niobium CST is selective for strontium both as Sr2+ and Sr(OH)(+). It is suggested that both radioisotopes of cesium and strontium may be efficiently extracted by a combination of a mixture of poorly crystalline CST and Nb-CST.

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