Removal of 85Sr, 134Cs, and 57Co radionuclides from acidic and neutral waste solutions by metal doped antimony silicates

Separation Science and Technology

Volumn 38, Issue 12-13, 2003, Pages 2995-3007

  Moller T ^a   Harjula, R ^a   Paajanen, A ^a  

^a UNIVERSITY OF HELSINKI   (Finland)

Author keywords

Cesium; Cobalt; Hydrous metal oxide; Ion exchange; Nuclear waste; Pyrochlore; Strontium

Indexed keywords

CESIUM; COBALT; DOPING (ADDITIVES); RADIOACTIVE WASTES; REMOVAL; SILICATES; STRONTIUM; TUNGSTEN; ZEOLITES;

PYROCHLORES;

RADIOISOTOPES;

CESIUM 134; COBALT 57; SILICATE; STRONTIUM 85;

ANTIMONY; CESIUM; COBALT; ION EXCHANGE; NUCLEAR POWER; POLLUTANT REMOVAL; STRONTIUM; WASTE;

ALKALINITY; CONFERENCE PAPER; DIFFUSION COEFFICIENT; NUCLEAR WASTE; PERFORMANCE; RADIOACTIVE WASTE DISPOSAL; SCREENING;

EID: 0042026702     PISSN: 01496395     EISSN: None     Source Type: Journal    
DOI: 10.1081/SS-120022583     Document Type: Conference Paper

References (20)

1. 6+. J. Mater. Chem. 2001, 11 (5), 1526.
2. Harjula, R.; Möller, T.; Amin, S.; Dyer, A.; Pillinger, M.; Newton, J.; Tusa, E.; Webb, M. Antimony silicate sorbent for removal of metal ions. International Patent Application WO 99/59161, 1999.
3. Dyer, A.; Pillinger, M.; Harjula, R.; Amin, S. Sorption characteristics of radionuclides on synthetic birnessite-type layered manganese oxides. J. Mater. Chem. 2000, 10, 1867.
4. Dyer, A.; Pillinger, M.; Newton, J.; Harjula, R.; Möller, T.; Amin, S. Sorption behavior of radionuclides on crystalline synthetic tunnel manganese oxides. Chem. Mater. 2000, 12, 3798.
5. Anthony, R.G.; Dosch, R.G.; Philip, C.V. Method of Using Novel Silicotitanates. US Patent 6,110,378, 2000.
6. Walker, F.; Taylor, P.A.; Lee, D.D. Cesium removal from high pH, high salt wastewater using crystalline silicotitanate sorbent. Sep. Sci. Technol. 1999, 35 (6-7), 1167.
7. Lehto, J.; Brodkin, L.; Harjula, R.; Tusa, E. Separation of radioactive strontium from alkaline nuclear waste solutions with the highly effective ion exchanger Sr. Treat. Nucl. Technol. 1999, 127, 81.
8. Sylvester, P.; Behrens, E.A.; Graziano, G.M.; Clearfield, A. An assessment of inorganic ion exchange materials for the removal of strontium from simulated hanford tank wastes. Sep. Sci. Technol. 1999, 34 (10), 1981.
9. Harjula, R.; Lehto, J.; Paajanen, A.; Brodkin, L.; Tusa, E. Removal of radioactive cesium from nuclear waste solutions with the transition metal hexacyanoferrate ion exchanger Cs. Treat. Nucl. Sci. Eng. 2001, 137, 206.
10. Qureshi, M.; Varshney, K.G. Inorganic Ion Exchangers in Chemical Analysis; CRC Press: Boca Raton, FL, 1991; 57-90.
11. Paajanen, A.; Lehto, J.; Santapakka, T.; Morneau, J.P. Sorption of cobalt on activated carbons from aqueous solutions. Sep. Sci. Technol. 1997, 32 (1-4), 813.
12. Clearfield, A. Inorganic Ion Exchange Materials; CRC Press: Boca Raton, FL, 1982; 197-246.
13. Abe, M.; Ito, T. Synthetic inorganic ion exchange materials. X. Preparation and properties of so-called antimonic(V) acid. Bull. Chem. Soc. Jpn 1968, 41, 333.
14. Baetsle, L.H.; Huys, D.J. Structure and ion exchange characteristics of polyantimonic acid. Inorg. Nucl. Chem. 1968, 30, 639.
15. Konecny, A.; Kourim, V. Recovery of Strontium by Means of a Polyantimonic(V) Acid Cation Exchanger. Radiochem. Radioanal. Lett. 1969, 2 (2), 47.
16. Varshney, K.G.; Rani, S. Ion exchange kinetics of some divalent metal ions on crystalline antimonic acid and antimony(V) silicate cation exchangers. React. Polym. 1985, 3, 231.
17. Subramanian, M.A.; Aravamudan, G.; Subba Rao, G.V. Oxide pyrochlores - a review. Prog. Sol. State Chem. 1983, 15, 55.
18. Helfferich, F.G. Ion Exchange; Dover Science: Mineola, NY, 1995.
19. Möller, T.; Clearfield, A.; Harjula, R. Preparation of hydrous mixed metal oxides of Sb, Nb, Si, Ti and W with a pyrochlore structure and exchange of radioactive cesium and strontium ion into the materials. Micropor. Mesopor. Mater. 2002, 54 (1-2), 187.
20. Harjula, R.; Lehto, J.; Tusa, E.; Paavola, A. Industrial scale removal of cesium with hexacyanoferrate exchanger-process development. Nucl. Technol. 1994, 107, 272.