Environmentally clean ceramics manufacture with the application of hazardous car production sludge and galvanic process glass waste

Author(s):  
Vsévolod Mymrin ◽  
Kirill Alekseev ◽  
Monica A. Avanci ◽  
Paulo H. B. Rolim ◽  
Cleber L. Pedroso ◽  
...  
Keyword(s):  
2018 ◽  
Author(s):  
Rebecca M. Chamberlin ◽  
Ming Tang ◽  
Rosendo Borjas Nevarez ◽  
Gordon Dennis Jarvinen ◽  
Daniel Koury ◽  
...  

2021 ◽  
Author(s):  
Ibtissam Abalouch ◽  
Siham Sakami ◽  
Fatima Ezzahera Elabbassi ◽  
Lahcen Boukhattem

2017 ◽  
Vol 20 (suppl 2) ◽  
pp. 393-398
Author(s):  
Talita Faria Santos ◽  
Herval Ramos Paes Junior ◽  
José Nilson França Holanda

2013 ◽  
Vol 46 (12) ◽  
pp. 2135-2144 ◽  
Author(s):  
A. M. Moncea ◽  
A. Badanoiu ◽  
M. Georgescu ◽  
S. Stoleriu

1993 ◽  
Vol 333 ◽  
Author(s):  
Maury E. Morgenstein ◽  
Don L. Shettel

ABSTRACTObsidian and basaltic glass are opposite end-members of natural volcanic glass compositions. Syngenetic and diagenetic tensile failure in basaltic glass (low silica glass) is pervasive and provides abundant alteration fronts deep into the glass structure. Perlitic fracturing in obsidian (high silica glass) limits the alteration zones to an “onion skin” geometry. Borosilicate waste glass behaves similarly to the natural analog of basaltic glass (sideromelane).During geologic time, established and tensile fracture networks form glass cells (a three-dimensional reticulated pattern) where the production of new fracture surfaces increases through time by geometric progression. This suggests that borosilicate glass monoliths will eventually become rubble. Rates of reaction appear to double for every 12C° of temperature increase. Published leach rates suggest that the entire inventory of certain radionuclides may be released during the 10,000 year regulatory time period. Steam alteration prior to liquid attack combined with pervasive deep tensile failure behavior may suggest that the glass waste form is not license defensible without a metallic- and/or ceramic-type composite barrier as an overpack.


2021 ◽  
Vol 1808 (1) ◽  
pp. 012012
Author(s):  
Wisnu Ari Prasetyo ◽  
Ernawati Sri Sunarsih ◽  
Taufiq Lilo Adi Sucipto ◽  
Kundari Rahmawati

2014 ◽  
Vol 5 (2) ◽  
pp. 136-145 ◽  
Author(s):  
Rosa Taurino ◽  
Isabella Lancellotti ◽  
Luisa Barbieri ◽  
Cristina Leonelli

2008 ◽  
Vol 1107 ◽  
Author(s):  
Carol M. Jantzen ◽  
James C. Marra

AbstractVitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. At the Savannah River Site (SRS) actual HLW tank waste has successfully been processed to stringent product and process constraints without any rework into a stable borosilicate glass waste since 1996. A unique “feed forward” statistical process control (SPC) has been used rather than statistical quality control (SQC). In SPC, the feed composition to the melter is controlled prior to vitrification. In SQC, the glass product is sampled after it is vitrified. Individual glass property models form the basis for the “feed forward” SPC. The property models transform constraints on the melt and glass properties into constraints on the feed composition. The property models are mechanistic and depend on glass bonding/structure, thermodynamics, quasicrystalline melt species, and/or electron transfers. The mechanistic models have been validated over composition regions well outside of the regions for which they were developed because they are mechanistic. Mechanistic models allow accurate extension to radioactive and hazardous waste melts well outside the composition boundaries for which they were developed.


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