Research output: Contribution to Journal/Magazine › Journal article › peer-review
Research output: Contribution to Journal/Magazine › Journal article › peer-review
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TY - JOUR
T1 - Tungsten bronze-based nuclear waste form ceramics. Part 2: Conversion of granular microporous tungstate-polyacrylonitrile (PAN) composite adsorbents to leach resistant ceramics
AU - Griffith, Christopher S.
AU - Sebesta, Ferdinand
AU - Hanna, John V.
AU - Yee, Patrick
AU - Drabarek, Elizabeth
AU - Smith, Mark E.
AU - Luca, Vittorio
PY - 2006
Y1 - 2006
N2 - Conversion of a granular molybdenum-doped, hexagonal tungsten bronze (MoW-HTB)-polyacrylonitrile (PAN) composite adsorbent to a leach resistant ceramic waste form capable of immobilizing adsorbed Cs+ and Sr2+ has been achieved by heating in air at temperatures in the range 600-1200 degrees C. Thermal treatment of the Cs- and Sr-loaded composite material at 1000 degrees C was sufficient to invoke a 60% reduction in volume of the composite while still retaining its spherical morphology. Cs-133 MAS NMR studies of this sample suite at 9.4 T and 14.1 T showed that multiple Cs sites are present throughout the entire thermal treatment range. Scanning electron microscopy investigations of the phase assemblages resulting from thermal treatment demonstrated that the full complement of Cs, and the majority of Sr, partitions into HTB phases (A(0.16-0.3)MO(3); A = Cs+, Sr2+ and Na+; M = Mo, W). The potentially reducing conditions resulting from the removal of the PAN matrix or the presence of high concentrations of Na+ relative to either Cs+ or Sr2+ does not retard the formation of the high temperature HTB phases. The fraction of Cs+ and Sr2+ leached from the tungstate phase assemblages was superior or comparable with cesium hollandite (Cs0.8Ba0.4Ti8O18; f = approximate to 8 x 10(-5); rate = <1.2 x 10(-4) g/m(2)/day) and strontium titanate (SrTiO3; f = 3.1 x 10(-3); rate = 2.63 x 10(-4) g/m(2)/day), respectively, using a modified PCT test in Millipore water at 90 degrees C. Furthermore, where aggressive leaching conditions were employed (0.1 M HNO3; 150 degrees C; 4 days), the tungstate phase assemblages displayed leach resistance almost two orders of magnitude greater than the reference phases.
AB - Conversion of a granular molybdenum-doped, hexagonal tungsten bronze (MoW-HTB)-polyacrylonitrile (PAN) composite adsorbent to a leach resistant ceramic waste form capable of immobilizing adsorbed Cs+ and Sr2+ has been achieved by heating in air at temperatures in the range 600-1200 degrees C. Thermal treatment of the Cs- and Sr-loaded composite material at 1000 degrees C was sufficient to invoke a 60% reduction in volume of the composite while still retaining its spherical morphology. Cs-133 MAS NMR studies of this sample suite at 9.4 T and 14.1 T showed that multiple Cs sites are present throughout the entire thermal treatment range. Scanning electron microscopy investigations of the phase assemblages resulting from thermal treatment demonstrated that the full complement of Cs, and the majority of Sr, partitions into HTB phases (A(0.16-0.3)MO(3); A = Cs+, Sr2+ and Na+; M = Mo, W). The potentially reducing conditions resulting from the removal of the PAN matrix or the presence of high concentrations of Na+ relative to either Cs+ or Sr2+ does not retard the formation of the high temperature HTB phases. The fraction of Cs+ and Sr2+ leached from the tungstate phase assemblages was superior or comparable with cesium hollandite (Cs0.8Ba0.4Ti8O18; f = approximate to 8 x 10(-5); rate = <1.2 x 10(-4) g/m(2)/day) and strontium titanate (SrTiO3; f = 3.1 x 10(-3); rate = 2.63 x 10(-4) g/m(2)/day), respectively, using a modified PCT test in Millipore water at 90 degrees C. Furthermore, where aggressive leaching conditions were employed (0.1 M HNO3; 150 degrees C; 4 days), the tungstate phase assemblages displayed leach resistance almost two orders of magnitude greater than the reference phases.
U2 - 10.1016/j.jnucmat.2006.06.018
DO - 10.1016/j.jnucmat.2006.06.018
M3 - Journal article
VL - 358
SP - 151
EP - 163
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 2-3
ER -