For a treatment of molten salt wastes generated from a pyroprocessing of oxide spent fuel, we had suggested a stable chemical route, named GRSS (Gel-Route Stabilization & Solidification), and a subsequent consolidation method. By using this method, a series of monolithic wasteforms with different conditions were fabricated, and then their physicochemical properties were investigated. A simulated salt containing 90wt% LiCl, 6.8wt% CsCl, and 3.2wt% SrCl2 was treated with a gel-forming material system, Si/Al/P = 0.4/0.4/0.2 and 0.35/0.35/0.3, and the gel-products were treated at 1100C° after mixing with borosilicate glass powder, where the salt loadings were about 16∼20wt%. The solidified products had a density of 2.3∼2.35g/cm3, a micro-hardness of 4.69∼4.72GPa, a glass transition temperature of 528∼537C°, and a thermal expansion coefficient of 1.65×10−7∼3.38×10−5/C°. Leaching results by the PCT-A method revealed leached rates, 10−3∼10−2g/m2day and 10−4∼10−3g/m2day for Cs and Sr, respectively. From the long-term ISO leaching test, the 900day-leached fraction of Cs and Sr predicted by a semi-empirical model were 0.89% and 0.39%. The leaching behaviors indicated that Cs would be immobilized into a Si-rich phase while Sr would be in a P-rich phase. The experimental results revealed that the GRSS method could be an alternative method for a solidification of radioactive molten salt wastes.
Skip Nav Destination
The 11th International Conference on Environmental Remediation and Radioactive Waste Management
September 2–6, 2007
Bruges, Belgium
Conference Sponsors:
- Nuclear Division and Environmental Engineering Division
ISBN:
978-0-7918-4339-0
PROCEEDINGS PAPER
Characteristics of Solidified Products Containing Radioactive Molten Salt Waste
In-Tae Kim,
In-Tae Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Hwan-Seo Park,
Hwan-Seo Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Yong-Zun Cho,
Yong-Zun Cho
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Kwang-Wook Kim,
Kwang-Wook Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Seong-Won Park,
Seong-Won Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Eung-Ho Kim
Eung-Ho Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
In-Tae Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Hwan-Seo Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
Yong-Zun Cho
Korea Atomic Energy Research Institute, Daejeon, South Korea
Kwang-Wook Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Seong-Won Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
Eung-Ho Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Paper No:
ICEM2007-7303, pp. 315-319; 5 pages
Published Online:
May 29, 2009
Citation
Kim, I, Park, H, Cho, Y, Kim, K, Park, S, & Kim, E. "Characteristics of Solidified Products Containing Radioactive Molten Salt Waste." Proceedings of the The 11th International Conference on Environmental Remediation and Radioactive Waste Management. 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Bruges, Belgium. September 2–6, 2007. pp. 315-319. ASME. https://doi.org/10.1115/ICEM2007-7303
Download citation file:
8
Views
0
Citations
Related Proceedings Papers
Related Articles
Nanostructuring Borosilicate Glass With Near-Field Enhanced Energy Using a Femtosecond Laser Pulse
J. Heat Transfer (January,2007)
Effect of Addition of Nano-Al 2 O 3 and Copper Particulates and Heat Treatment on the Tensile Response of AZ61 Magnesium Alloy
J. Eng. Mater. Technol (July,2013)
Warpage of Plastic IC Packages as a Function of Processing Conditions
J. Electron. Packag (September,2001)
Related Chapters
Utilities’ Perspective of Spent Fuel Storage
Global Applications of the ASME Boiler & Pressure Vessel Code
Spent Fuel and Decommissioning
Decommissioning Handbook
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition