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Filename 105901.pdf
filesize 1.7 MB
Version 1
date September 2010
Downloaded 588 times
Category Advanced Nuclear Energy, Bureau of Land Management, Defense Waste Management, Energy Security, Manual, Modeling and Analysis, Nuclear Energy, Nuclear Energy Safety, Renewable Energy
author Yifeng Wang, Huizhen Gao, C. Jeffrey Brinker, Yongliang Xiong, Kathleen Holt, Andy Miller, Phillip Pohl, Nathan Ockwig, Mark A. Rodriquez, Denise N. Bencoe, Hernesto Tellez, Jessica Nicole Kruichak, Rigney Turnham, and Andrew Wilson Murphy
report-id SAND2010-5901

The United States is now re-assessing its nuclear waste disposal policy and re-evaluating the option of moving away from the current once-through open fuel cycle to a closed fuel cycle. In a closed fuel cycle, used fuels will be reprocessed and useful components such as uranium or
transuranics will be recovered for reuse. During this process, a variety of waste streams will be generated. Immobilizing these waste streams into appropriate waste forms for either interim storage or long-term disposal is technically challenging. Highly volatile or soluble radionuclides such as iodine (129I) and technetium (99Tc) are particularly problematic, because both have long
half-lives and can exist as gaseous or anionic species that are highly soluble and poorly sorbed by natural materials. Under the support of Sandia National Laboratories (SNL) Laboratory- Directed Research & Development) (LDRD), we have developed a suite of inorganic nanocomposite materials (SNL-NCP) that can effectively entrap various radionuclides, especially for 129I and 99Tc. In particular, these materials have high sorption capabilities for
iodine gas. After the sorption of radionuclides, these materials can be directly converted into nanostructured waste forms. This new generation of waste forms incorporates radionuclides as nano-scale inclusions in a host matrix and thus effectively relaxes the constraint of crystal structure on waste loadings. Therefore, the new waste forms have an unprecedented flexibility to
accommodate a wide range of radionuclides with high waste loadings and low leaching rates. Specifically, we have developed a general route for synthesizing nanoporous metal oxides from inexpensive inorganic precursors. More than 300 materials have been synthesized and characterized with x-ray diffraction (XRD), BET surface area measurements, and transmission electron microscope (TEM). The sorption capabilities of the synthesized materials
have been quantified by using stable isotopes I and Re as analogs to 129I and 99Tc. The results have confirmed our original finding that nanoporous Al oxide and its derivatives have high I sorption capabilities due to the combined effects of surface chemistry and nanopore confinement. We have developed a suite of techniques for the fixation of radionuclides in metal oxide nanopores. The key to this fixation is to chemically convert a target radionuclide into a less volatile or soluble form. We have developed a technique to convert a radionuclide-loaded nanoporous material into a durable glass-ceramic waste form through calcination. We have shown that mixing a radionuclide-loaded getter material with a Na-silicate solution can
effectively seal the nanopores in the material, thus enhancing radionuclide retention during waste
form formation. Our leaching tests have demonstrated the existence of an optimal vitrification temperature for the enhancement of waste form durability. Our work also indicates that silver may not be needed for I immobilization and encapsulation.