Respirable Fines Produced by Impacts of Simulated Alternative High-Level Waste Materials

1981 ◽  
Vol 6 ◽  
Author(s):  
Leslie J. Jardine ◽  
Gerald T. Reedy ◽  
William J. Mecham
Keyword(s):  
Fragment Size ◽  
High Level Waste ◽  
Size Distributions ◽  
Savannah River ◽  
Waste Forms ◽  
Mass Fractions ◽  
High Silica ◽  
Weight Impact ◽  
High Level ◽  
Spinel Ceramic

ABSTRACTStandardized comparative drop weight impact tests were conducted on solid alternative waste forms under consideration for immobilizing Savannah River Laboratory (SRL) defense wastes. The fragment size distributions were measured in the size ranges of ֮5 to 8000 μm. All waste form fragment size distributions could be described accurately by lognormal plots. Respirable sizes (≤10 μm) were measured. Borosilicate glass and SYNROC specimens yielded the same mass fractions of respirable sizes; FUETAP concrete, high silica and alkoxide glass specimens yielded ֮2–3 times more mass fractions of particles of respirable sizes, whereas tailored (Spinel) ceramic specimens yielded the smallest mass fractions of respirable sizes, ֮2–1/2 times less.

An Experimental Comparison of Alternative Solid Forms for Savannah River High-Level Wastes

1981 ◽  
Vol 6 ◽  
Author(s):  
John A. Stone
Keyword(s):  
Borosilicate Glass ◽  
Silica Glass ◽  
Deionized Water ◽  
Experimental Comparison ◽  
Savannah River ◽  
Waste Forms ◽  
High Silica ◽  
High Level ◽  
Selection Of ◽  
High Aluminum

ABSTRACTSamples of borosilicate glass, high-silica glass, tailored ceramic, and SYNROC, incorporating simulated Savannah River high-level defense waste sludges, were leached by the MCC-1 procedure for times up to 28 days. Cesium, uranium, and cerium leach rates are reported for waste forms containing a composite sludge, at 40°C in deionized water, and at 90°C in deionized water, silicate water, and brine. The ordering of the waste forms from best to worst differs for each element leached, and none of the forms show a clear advantage for all the key radwaste elements. Some cesium leach rates for forms containing high-aluminum or high-iron sludges also are presented. So far, only small effects of sludge type have been observed, with one exception. This study is one of several inputs for selection of an alternative waste form for Savannah River waste.

Titanate Waste Forms for High Level Waste — An Evaluation of Materials and Processes

1981 ◽  
pp. 123-130 ◽  
Author(s):  
R. G. Dosch ◽  
A. W. Lynch ◽  
T. J. Headley ◽  
P. F. Hlava
Keyword(s):  
High Level Waste ◽  
Waste Forms ◽  
High Level

Adaptation of CCIM Technology for HLW Treatment: Results of Research and Development

2010 ◽  
Author(s):  
Vladimir Lebedev ◽  
Sergey Stefanovsky ◽  
Alexander Kobelev ◽  
Fyodor Lifanov ◽  
Sergey Dmitriev
Keyword(s):  
High Level Waste ◽  
Cold Crucible ◽  
Savannah River ◽  
Treatment Results ◽  
Auxiliary Equipment ◽  
Automated Control ◽  
Automated Control System ◽  
New Perspective ◽  
High Level ◽  
River Site

Results of feasibility tests of application of Cold Crucible Inductive Melting (CCIM) technology to high level waste (HLW) treatment on examples of Savannah River Site, USA, and PA “Mayak”, Russia, HLW, carried out at SIA Radon, and results of design of new perspective bench-scale HLW vitrification facility are presented in this report. Full-scale low level waste (LLW) vitrification plant is under operation at Radon since 2003. Successful Radon experience aroused an interest to this technology from US DOE. Since 2001 Radon performed tests on vitrification of surrogates of various types of HLW stored at US DOE Sites. Process variables were determined and vitrified wastes were characterized in details. Since 2007 Radon was a subcontractor in the project on design and construction of a new CCIM based vitrification facility at PA “Mayak”. From preliminary tests on Mayak HLW surrogates the main technological features of CCIM process were determined and principles of the process control were formulated. Radon performed the design of the cold crucible and automated control system. On the base of analysis of previously and newly obtained data the main requirements to designing of cold crucible melters and auxiliary equipment, intended for actual HLW treatment, were worked out.

Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems

1986 ◽  
Vol 73 (2) ◽  
pp. 139-139
Author(s):  
Edward J. Hennelly ◽  
E. I. Du Pont de Nemours
Keyword(s):  
Borosilicate Glass ◽  
High Level Waste ◽  
Waste Forms ◽  
High Level

Dose-Dependence of Pb-Ion Implantation Damage in Zirconolite, Hollandite, and Zircon

1981 ◽  
Vol 11 ◽  
Author(s):  
T. J. Headley ◽  
G. W. Arnold ◽  
C. J. M. Northrup
Keyword(s):  
Radiation Damage ◽  
Structural Damage ◽  
Accelerated Aging ◽  
Dose Dependence ◽  
High Level Waste ◽  
Long Term Stability ◽  
Waste Forms ◽  
Recent Approach ◽  
High Level

The long-term stability of nuclear waste forms is an important consideration in their selection for safe disposal of radioactive waste. Stability against long-term radiation damage is particularly difficult to assess by short-term laboratory experiments. Much of the displacement damage in high-level waste forms will be generated by heavy recoil nuclei emitted during the α-decay process of long-lived actinide elements. Hence, an accelerated aging test which reliably simulates the α-recoil damage accumulated during thousands of years of storage is desirable. One recent approach to this simulation is to implant the waste form with heavy Pb-ions.I- 6 If the validity of this approach is to be fully assessed, two important questions which have not yet been investigated must be answered.(1) Is the structural damage, including cumulative effects, similar for irradiation by Pb-ions and a-recoil nuclei in a given material? (2) Is the dose-dependence of the accumulated damage similar? The purpose of this investigation was to assess the extent of these similarities in selected materials. We utilized transmission electron microscopy (TEM) to characterize the radiation damage and measure its dose-dependence.

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