The immobilization radioiodine produced from used nuclear fuel reprocessing is a growing priority for research and development of nuclear waste forms. This review provides a comprehensive summary of the current issues surrounding processing and containment of 129I, the isotope of greatest concern due to long half-life and potential incorporation into the human body. Strategies for disposal of iodine, both wet scrubbing and solid sorbents, are discussed, as well as potential iodine waste streams for insertion into an immobilization process. Next, consideration of direct disposal of salts, incorporation into glasses, ceramics, cements, and other phases is addressed. The bulk of the review is devoted to an assessment of various sorbents for iodine and waste forms described in the literature, particularly inorganic minerals, ceramics/minerals, and glasses. This review also contains recommendations for future research needed to address radioiodine immobilization materials and processes.
Revised: April 28, 2016 |
Published: March 1, 2016
Citation
Riley B.J., J.D. Vienna, D.M. Strachan, J.S. McCloy, and J.L. Jerden. 2016.Materials and Processes for the Effective Capture and Immobilization of Radioiodine: A Review.Journal of Nuclear Materials 470.PNNL-SA-111665.doi:10.1016/j.jnucmat.2015.11.038