scholarly journals Nepheline crystallization and the residual glass composition: Understanding waste glass durability

2020 ◽  
Vol 11 (4) ◽  
pp. 649-659
Author(s):  
Devon L. McClane ◽  
Jake W. Amoroso ◽  
Kevin M. Fox ◽  
Madison C. Hsieh ◽  
Matthew R. Kesterson ◽  
...  
1999 ◽  
Vol 556 ◽  
Author(s):  
H. Gan ◽  
A. C. Buechele ◽  
C.-W. Kim ◽  
X. Huang ◽  
R. K. Mohr ◽  
...  

AbstractInconel-690, a Cr-Ni-Fe-based “superalloy,” has become the material of choice for electrodes in joule-heated waste glass melters and is currently employed in the high-level nuclear waste vitrification systems at West Valley and DWPF, as well as in GTS Duratek's privatized M-Area mixed waste vitrification facility at Savannah River. Future applications of joule-heated vitrification technologies will necessitate an assessment of the limits of performance of this material under more demanding conditions than have been studied previously. In this work, Inconel 690 electrodes were tested in several simulated sodium-rich aluminosilicate waste glasses in wide ranges of AC current density, electrical waveform, temperature, and glass composition.


2019 ◽  
Vol 510 ◽  
pp. 158-165 ◽  
Author(s):  
R.B. Nuernberg ◽  
T.S. Bello ◽  
V.M. Fokin ◽  
E.D. Zanotto ◽  
A.C.M. Rodrigues

1991 ◽  
Vol 257 ◽  
Author(s):  
Alfred Schneider ◽  
Kang-Wen K. Li ◽  
Ray F. Schumacher

ABSTRACTAn on-line method is described for the near-continuous monitoring of the composition of a molten radioactive waste glass or, alternatively, for signaling a deviation from the target composition of a waste glass. The principle of this method, proposed by A. Schneider in 1986, is founded on the relation between two specific physical properties and composition in a ternary system. Most glasses currently considered as waste forms can be represented as pseudo-ternary systems. The pair of properties especially well suited for this purpose are the viscosity and density of the molten glass. A novel viscometry method was developed which uses the remotely determined rise velocity of carefully metered gas bubbles. The monitoring method was tested successfully with simulated Savannah River waste glasses. An integrated probe was conceived for a Joule-heated melter for the on-line determination of viscosity, temperature, density, and liquid level. A computer program calculates the glass composition from the measured data, using information from a previously developed data base.


2014 ◽  
Vol 384 ◽  
pp. 32-40 ◽  
Author(s):  
Pavel Hrma ◽  
Brian J. Riley ◽  
Jarrod V. Crum ◽  
Josef Matyas

2000 ◽  
Vol 663 ◽  
Author(s):  
P. Loiseau ◽  
D. Caurant ◽  
N. Baffier ◽  
L. Mazerolles ◽  
C. Fillet

ABSTRACTZirconolite (CaZrTi2O7) based glass-ceramics designed for the specific immobilization of plutonium wastes or minor actinides (Np, Am, Cm) from high level radioactive wastes were investigated. To reach an efficient double containment, actinides must be preferentially located in the crystalline phase, which is homogeneously dispersed in a calcium aluminosilicate residual glass. Several heat treatments (between 950° and 1350°C) of a parent glass belonging to the SiO2-Al2O3-CaO system and containing TiO2 and ZrO2 were performed to prepare glass-ceramics. Trivalent minor actinides were simulated introducing Nd2O3 in the glass composition. Electron microscopy, X-ray diffraction (XRD) and thermal analysis have shown that devitrification processes in the bulk and on glass surface are different. They lead to the crystallization of zirconolite in the bulk and to a mixture of titanite (CaTiSiO5) and anorthite (CaAl2Si2O8) near the surface. For heat treatment temperatures greater than or equal to 1250°C, baddeleyite (m-ZrO2) crystals form at the expense of zirconolite in the bulk of glass-ceramics. XRD indicates that the order in zirconolite Ca/Zr planes increases with heating temperature. At the same time, extended defects density decreases.


1996 ◽  
Vol 465 ◽  
Author(s):  
I. A. Sobolev ◽  
M. I. Ojovan ◽  
O.G Batyukhnova ◽  
N. V. Ojovan ◽  
T. D. Scherbatova

ABSTRACTThe behaviour of waste glass was investigated under open site disposal conditions. This glass was produced by vitrification of intermediate level radioactive waste from nuclear power plants. Two types of borosilicate glasses were obtained for two different reactor wastes, WWER and RBM.K. Leaching and alteration mechanisms are discussed as well as the data processing technique used for these long term tests. The decay of radionuclides was accounted for in order to obtain correct results. The leaching factors obtained can be used for the assesment of radionuclide retention. Discontinuous leaching of Cs-137 has been observed during more than 8 years testing time. The fluctuating leaching rate depends on glass composition. The average leaching rate remains within (0.4 – 4) μg/sq. sm·day.Alteration of waste glass includes the formation of surface layers and cracks on the glass surface. SEM analysis of glass was used to show these surface layers. The thickness of the layers was determined to be within 2–6 μm. The structure of these layers depends on glass composition and the interfacing environment.


2014 ◽  
Vol 97 (10) ◽  
pp. 3135-3142 ◽  
Author(s):  
John D. Vienna ◽  
Dong-Sang Kim ◽  
Isabelle S. Muller ◽  
Greg F. Piepel ◽  
Albert A. Kruger

Author(s):  
M. A. McCoy

Transformation toughening by ZrO2 inclusions in various ceramic matrices has led to improved mechanical properties in these materials. Although the processing of these materials usually involves standard ceramic powder processing techniques, an alternate method of producing ZrO2 particles involves the devtrification of a ZrO2-containing glass. In this study the effects of glass composition (ZrO2 concentration) and heat treatment on the morphology of the crystallization products in a MgO•Al2•SiO2•ZrO2 glass was investigated.


2015 ◽  
Vol 48 (6) ◽  
pp. 145-150
Author(s):  
Bong-Ki Ryu ◽  
Il-Gu Kim ◽  
Young-Seok Kim ◽  
Jong-Hwan Kim ◽  
Jae-Yeop Jung ◽  
...  

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