scholarly journals Removal of TcO4– from Representative Nuclear Waste Streams with Layered Potassium Metal Sulfide Materials

2016 ◽  
Vol 28 (11) ◽  
pp. 3976-3983 ◽  
Author(s):  
James J. Neeway ◽  
R. Matthew Asmussen ◽  
Amanda R. Lawter ◽  
Mark E. Bowden ◽  
Wayne W. Lukens ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Metal Sulfide ◽  
Waste Streams

SREX: A NEWPROCESS FOR THE EXTRACTION AND RECOVERY OF STRONTIUM FROM ACIDIC NUCLEAR WASTE STREAMS

1991 ◽  
Vol 9 (1) ◽  
pp. 1-25 ◽  
Author(s):  
E. Philip Horwitz ◽  
Mark L. Dietz ◽  
Dan E. Fisher
Keyword(s):  
Nuclear Waste ◽  
Waste Streams

scholarly journals A Recovery Process of Strontium from Acidic Nuclear Waste Streams

1997 ◽  
Vol 32 (10) ◽  
pp. 1725-1737 ◽  
Author(s):  
M. Draye ◽  
G. Le Buzit ◽  
J. Foos ◽  
A. Guy ◽  
B. Leclere ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Recovery Process ◽  
Waste Streams

scholarly journals Apatite- and Monazite-Bearing Glass-Crystal Composites for the Immobilization of Low-Level Nuclear and Hazardous Wastes

1995 ◽  
Vol 412 ◽  
Author(s):  
D. J. Wronkiewicz ◽  
S. F. Wolf ◽  
T. S. DiSanto
Keyword(s):  
Transition Metals ◽  
Nuclear Waste ◽  
Toxic Metals ◽  
Hazardous Wastes ◽  
Waste Streams ◽  
Waste Forms ◽  
Glass Crystal ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Crystal Composite

AbstractThis study demonstrates that glass-crystal composite waste forms can be produced from waste streams containing high proportions of phosphorus, transition metals, and/or halides. The crystalline phases produced in crucible-scale melts include apatite, monazite, spinels, and a Zr-Si-Fe-Ti phase. These phases readily incorporated radionuclide and toxic metals into their crystal structures, while corrosion tests have demonstrated that glass-crystal composites can be up to 300-fold more durable than simulated high-level nuclear waste glasses, such as SRL 202U.

Development of New Cs+ Ion-Selective Electrode with Alkyl-Bridged Calix[4]arene Crown-6 Compounds for the Determination of Cs+ in Nuclear Waste Streams

2017 ◽  
Vol 2 (32) ◽  
pp. 10347-10353 ◽  
Author(s):  
Pentapati S. Ramanjaneyulu ◽  
Kshama Kundu ◽  
Manoj K. Sharma ◽  
Sandeep K. Nayak
Keyword(s):  
Nuclear Waste ◽  
Ion Selective Electrode ◽  
Waste Streams ◽  
Selective Electrode

Applying Best Practical Environmental Optioneering (BPEO) to a Complex Clean Up Programme: A Ponds and Silos Case Study

2009 ◽  
Author(s):  
Simon Candy
Keyword(s):  
Decision Making ◽  
Nuclear Waste ◽  
Informed Decision ◽  
Nuclear Industry ◽  
Waste Stream ◽  
Informed Decision Making ◽  
Nuclear Wastes ◽  
Waste Streams ◽  
Selection Of

The use of Best Practical Environmental Optioneering (BPEO) has long been part of informed decision making within the Nuclear Industry. However, BPEO has typically been applied to specific and discrete objectives, for example the selection of a technology to treat a particular nuclear waste stream. While this has sometimes been extended to cover a number of objectives, no one had applied BPEO to a programme of the size and complexity of that associated with Legacy Ponds & Silos at Sellafield. The programme, spanning more than 30 years, includes a range of different objectives covering ongoing management, recovery, conditioning, storage and ultimately disposal of nuclear wastes. This range of activities is applied across a number of facilities containing multiple, significant waste streams. This paper explains how BPEO was applied to the Legacy Ponds & Silos programme and discussed some of the learning resulting from that exercise.

The Effect of Temperature on the Redox Constraints for the Processing of High-Level Nuclear Waste into a Glass Waste Form

1989 ◽  
Vol 176 ◽  
Author(s):  
Henry D. Schreiber ◽  
Charlotte W. Schreiber ◽  
Margaret W. Riethmiller ◽  
J. Sloan Downey
Keyword(s):  
Oxygen Fugacity ◽  
Nuclear Waste ◽  
Metal Sulfide ◽  
Effect Of Temperature ◽  
Processing Temperature ◽  
Savannah River ◽  
Glass Waste ◽  
Oxidation Reduction ◽  
High Level Nuclear Waste ◽  
High Level

ABSTRACTThe oxidation-reduction equilibria of selected multivalent elements in an alkali borosilicate glass melt (Savannah River Laboratory frit #131) were measured as a function of the imposed oxygen fugacity over the temperature range from 950°C to 1350°C. Redox constraints on the processing of high-level nuclear waste into the glass melt require that the prevailing oxygen fugacity be about 10−5 to 10−12 Zatm at 950°C, about 10−2 to 10−9 atm at 1150°C, and about 100 to 10−7 atm at 1350°C. Such conditions circumvent foaming under oxidizing situations and metal/sulfide precipitation if the system becomes too reducing. The defined oxygen fugacity ranges correspond to the previously prescribed range of 0.1 to 0.5 for the [Fe2+]/[Fe3+] ratio in the resulting glass, independent of the processing temperature from 950°C to 1350°C.

scholarly journals Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron

2007 ◽  
Vol 19 (23) ◽  
pp. 5703-5713 ◽  
Author(s):  
John G. Darab ◽  
Alexandra B. Amonette ◽  
Deborah S. D. Burke ◽  
Robert D. Orr ◽  
Sherman M. Ponder ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Zerovalent Iron ◽  
Waste Streams

scholarly journals Energetics of Salt-Bearing Sodalites, Na8Al6Si6O24X2 (X = SO4, ReO4, Cl, I): A Treatment Option for Pertechnetate-Enriched Nuclear Waste Streams

2020 ◽  
Vol 4 (11) ◽  
pp. 2153-2161
Author(s):  
Kristina Lilova ◽  
Eric M. Pierce ◽  
Lili Wu ◽  
Aaron M. Jubb ◽  
Tamilarasan Subramani ◽  
...  
Keyword(s):  
Treatment Option ◽  
Nuclear Waste ◽  
Waste Streams

Separation of Actinides(III) from Lanthanides(III) in Simulated Nuclear Waste Streams using 6,6′‐Bis‐(5,6‐dipentyl‐[1,2,4]triazin‐3‐yl)‐[2,2′]bipyridinyl (C5‐BTBP) in Cyclohexanone

2006 ◽  
Vol 24 (6) ◽  
pp. 823-843 ◽  
Author(s):  
Mikael Nilsson ◽  
Christian Ekberg ◽  
Mark Foreman ◽  
Michael Hudson ◽  
Jan‐Olov Liljenzin ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Waste Streams
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