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C. M. Jantzen, D. F. Bickford, K. G. Brown, A. D. Cozzi, C. C. Herman, J. C. Marra, D. K. Peeler, J. B. Pickett, R. F. Schumacher, M. E. Smith, J. C. Whitehouse and J. R. Zamecnik, “Savannah River Site Waste Vitrification Projects Initiated throughout the United States: Disposal and Recycle Options,” Westinghouse Savannah River Company, Aiken, 2000.

has been cited by the following article:

• TITLE: Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass

  AUTHORS: Nasir Hamodi, Kassandra Papadopoulou, Tristan Lowe, Timothy Abram

  KEYWORDS: Absorption Processes; Borosilicate Glass; Immobilization; Ion Exchange Resin; Radiation Damage

  JOURNAL NAME: New Journal of Glass and Ceramics, Vol.2 No.3, July 30, 2012

  ABSTRACT: The underground disposal of waste arising from the nuclear industry needs constant evaluation in order to improve upon it through minimizing the volume and cost by reducing the amount of glass used without compromising the safety of any leakage from the radioactive waste form. The immobilization of the spent resin (NRW-40) in borosilicate glass was investigated to meet the acceptance criteria for disposal of nuclear waste. The organic mixed bed resin in granular form was used as a waste target. The analysis of surrogate resin doped with radioactive and non-radioactive cesium (Cs) and cobalt (Co) was carried out to investigate their thermal and chemical properties and their compatibility with an alkaline borosilicate glass. The thermal analysis indicates that the structural damage caused by 1 mSv gamma radiation to the radioactive resin has altered its properties in comparison with the non-radioactive resin, same amount of cesium (8.88 wt%) and cobalt (1.88 wt%) were used in both resins. The immobilization of residue shows that the excess sulfur in the residue caused phase crystallization in the final glass matrix. It was found that the volatilization of Cs-137 and Co-60 from the successful radioactive resin-glass matrix (HG-3-IER-500) were more than that in the non-radioactive resin-glass matrix (HG-3-IEX-500). The study demonstrates comprehensive experimental and analytical works and shows that it is possible to minimise the volume of the waste while keeping the required safety levels, however further research needs to be carried out in this area.