Selective removal of cesium and strontium using porous frameworks from high level nuclear waste

2016 ◽  
Vol 52 (35) ◽  
pp. 5940-5942 ◽  
Author(s):  
Briana Aguila ◽  
Debasis Banerjee ◽  
Zimin Nie ◽  
Yongsoon Shin ◽  
Shengqian Ma ◽  
...  
Keyword(s):  
Ion Exchange ◽  
Aqueous Solutions ◽  
Nuclear Waste ◽  
Selective Removal ◽  
High Level Nuclear Waste ◽  
Presence And Absence ◽  
High Level ◽  
Exchange Properties ◽  
Competing Ions

A water stable MOF, MIL-101-SO3H, shows excellent Cs+ and Sr2+ ion exchange properties in aqueous solutions in the presence and absence of competing ions.

Initial Demonstration of the Vitrification of High-Level Nuclear Waste Sludge Containing an Organic Cs-Loaded Ion-Exchange Resin

1992 ◽  
Vol 294 ◽  
Author(s):  
N. E. Bibler ◽  
J. P. Bibler ◽  
M. K. Andrews ◽  
C. M. Jantzen
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Exchange Resin ◽  
Ion Exchange Resin ◽  
Waste Sludge ◽  
New Process ◽  
The Usa ◽  
High Level Nuclear Waste ◽  
High Level

ABSTRACTWhen immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. A resorcinol based organic ion exchange resin is used. This resin was then mixed with sludge and frit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. For example, use of the zeolite increases the amount of glass to be made and use of the organic precipitant produces benzene as a secondary waste stream. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. However, when resin is present in the feed, the glass becomes less durable due to the increased amount of Fe(II) caused by reduction of Fe(III) in the melt. Based on the durabilities of other waste glasses, this glass is still suitable as a canistered wasteform.

Transmutation of high-level nuclear waste by means of accelerator driven system

2013 ◽  
Vol 3 (1) ◽  
pp. 60-69 ◽  
Author(s):  
Hamid Aït Abderrahim ◽  
Didier De Bruyn ◽  
Gert Van den Eynde ◽  
Sidney Michiels
Keyword(s):  
Nuclear Waste ◽  
Driven System ◽  
High Level Nuclear Waste ◽  
Accelerator Driven System ◽  
High Level

Effect of Al and Fe sources on conversion of high-level nuclear waste feed to glass

2021 ◽  
pp. 153423
Author(s):  
José Marcial ◽  
Jaroslav Kloužek ◽  
Miroslava Vernerová ◽  
Pavel Ferkl ◽  
SeungMin Lee ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
High Level Nuclear Waste ◽  
High Level
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