By Committee on Radionuclide Separation Processes for High-Level Waste at the Savannah River Site, Board on Radioactive Waste Management, Board on Chemical Sciences and Technology, National Research Council
The U.S. division of strength (DOE) is nearing a call on tips on how to approach 30 million gallons of high-level radioactive waste salt strategies on the Savannah River web site in South Carolina to take away strontium, actinides, and cesium for immobilization in glass and eventual cargo to a geologic repository. the dep. is sponsoring examine and improvement (R&D) paintings on 4 replacement strategies and plans to take advantage of the implications to make a downselection selection in a June 2001 timeframe. The DOE asked that the nationwide examine Council aid tell this selection by means of addressing the subsequent charge:
1. evaluation the adequacy of the factors that would be utilized by the dep. to choose from one of the candidate methods lower than consideration;
2. evaluation the growth and result of the learn and improvement paintings that's being undertaken on those candidate procedures; and
three. check even if the technical uncertainties were sufficiently resolved to continue with downsizing the checklist of candidate processes.
Responses to the final issues are supplied during this document. Research and improvement on a Salt Processing replacement for High-Level Waste on the Savannah River Site focuses solely at the technical matters concerning the candidate techniques for radionuclide removing from high-level waste salt recommendations at SRS. The committee's period in-between record served as a reaction to the 1st aspect of this cost, and will be learn in Appendix B. In that document, the committee came upon that DOE's proposed standards are an appropriate foundation for choosing one of the candidate methods into account, yet that the factors shouldn't be applied in a manner that is dependent upon a unmarried numerical "total score."
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Extra resources for Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site
Committee Conclusions on the CST Process Of the three cesium separation processes under consideration, it is the committee's judgment that CST has the most technical uncertainties and the highest technical risks. About this PDF file: This new digital representation of the original work has been recomposed from XML files created from the original paper book, not from the original typesetting files. Page breaks are true to the original; line lengths, word breaks, heading styles, and other typesetting-specific formatting, however, cannot be retained, and some typographic errors may have been accidentally inserted.
Please use the print version of this publication as the authoritative version for attribution. 47). Two other alternative adsorbents to MST, sodium nonatitanate (ST) and SrTreat® (proprietary), were also compared to MST for their ability to remove strontium and actinides. 15 µg/L of strontium remain in solution after treatment versus approximately 5 µg/L for MST after 107 hours). 5 µg/L of Pu remain versus 7 µg/L after 107 hours), while the rate for SrTreat® was significantly lower (approximately 90 µg/L of plutonium remain after 107 hours).
These precipitates include cancrinite and minor amounts of sodalite. In addition, the precipitation of aluminosilicates on CST was observed in waste simulant experiments (described below) at elevated temperatures (50-120 °C) and/or on prolonged exposure (86 days) to the simulants. Although fundamental understanding of the formation and impact of secondary minerals and phases has been enhanced through research, particularly with respect to the formation of new niobium phases, significant questions remain regarding aluminosilicate precipitation.