The Immobilization of Cesium and Strontium in Ceramic Materials Derived from Tungstate Sorbents
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7KH,PPRELOL]DWLRQRI&HVLXPDQG6WURQWLXPLQ&HUDPLF0DWHULDOV'HULYHGIURP 7XQJVWDWH6RUEHQWV Vittorio Luca, Elizabeth Drabarek, Christopher S. Griffith, Harriet Chronis, and James Foy Materials and Engineering Sciences, Australian Nuclear Science and Technology Organization, New Illawarra Road, Lucas Heights, NSW 2234, AUSTRALIA $%675$&7 The effective immobilization of Cs+ and/or Sr2+ sorbed on hexagonal tungsten oxide bronze (HTB) adsorbent materials can be achieved by heating in air at temperatures in the range 500 - 1000 °C. Crystalline powdered HTB materials formed by heating at 800 °C show leach characteristics comparable to Cs-containing hot-pressed hollandites in the pH range from 0 to 12. If the Cs-loaded HTB sorbents are pressed into pellets prior to calcination, ceramic monoliths can be prepared. Heating to temperatures in excess of 1250 °C results in the melting of the sorbent to form millimetre-sized crystals of bronzoid phases. Thermal analysis shows that melting of the cation-exchanged tungstate sorbents is initiated at temperatures as low as 850 °C and concludes by 1300 °C. The absence of any significant mass loss immediately after melting, as well as chemical analyses before and after melting, confirm that Cs is not volatilized to any significant extent at the temperatures required to generate durable, coarsely crystalline products. The melted bronzoid product is a multiphase ceramic in which Cs+ remains bound within, and appears to stabilize, the hexagonal bronze phase, even after complete melting at 1300 °C, while elements such as Sr2+ are present within other tungstate phases. The bronzoid chemical system appears capable of accommodating a wide range of other elements. Here we have demonstrated that modification of the sorbent properties by incorporation Mo does not impact severely on the durability of materials prepared below 1000 °C, even when exposed to strong acid (pH=1) and elevated temperature (150 °C). As an example, one-day MCC1 leach rates lower than 1x10-5 g/m2/day were measured using demineralized water at 90 °C for Cs-saturated Mo-doped sorbents that had been heated in air at 900 °C, while the fraction of Cs leached from powdered samples in 0.1 M HNO3 solutions at 150 °C for 4 days is only 4x10-3 g/m2/day. ,1752'8&7,21 In recent years there has been increasing international interest in the separation of 137Cs and Sr from radioactive waste liquids that are greater than about 10 years old because, although these radio nuclides account for only 1% of the mass, they are responsible for more than 99 % of the activity [1]. The approaches used for separating radio nuclides fall into two main groups; 1) solvent extraction and 2) ion exchange, with the latter process, in general, being technically less demanding. With the aim of achieving efficient separation of these elements, several inorganic ion exchange materials have been developed. Once the Cs+ and Sr2+ are extracted using the adsorbent there is a need for immobilization and disposal. One approach to the immobilization of the Cs-l
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