Rhenium volatilization in waste glasses
نویسندگان
چکیده
منابع مشابه
Rhenium solubility in borosilicate nuclear waste glass: implications for the processing and immobilization of technetium-99.
The immobilization of technetium-99 ((99)Tc) in a suitable host matrix has proven to be a challenging task for researchers in the nuclear waste community around the world. In this context, the present work reports on the solubility and retention of rhenium, a nonradioactive surrogate for (99)Tc, in a sodium borosilicate glass. Glasses containing target Re concentrations from 0 to 10,000 ppm [by...
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Article history: Received 16 September 2010 Received in revised form 22 December 2010 Available online 10 February 2011
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The treatment of lead-containing cathode-ray tube (CRT) glass is an important environmental issue. One approach is the removal of lead by chloride volatilization. In the present work, the reaction of CRT glass with PVC as the chlorinating agent and Ca(OH)2 as the chlorine absorber was investigated by thermogravimetric analysis (TGA) in air. Seven reaction steps occurring at different temperatur...
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A series of sodium borosilicate glasses were synthesized with KReO4 or Re2O7, to 10,000 ppm (1 mass%) target Re, to assess effects of large concentrations of rhenium on glass structure and fto estimate solubility of Tc, a radioactive component in low active waste nuclear glasses. Rhenium was used as a surrogate for Tc for laboratory testing, due to similarities in chemistry, ionic size, and red...
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ژورنال
عنوان ژورنال: Journal of Nuclear Materials
سال: 2015
ISSN: 0022-3115
DOI: 10.1016/j.jnucmat.2015.05.005