Screening of Candidate Low‐Temperature Glass Waste Forms for Technetium from Hanford Effluent Management Facility Evaporator Bottoms

2018 ◽  
Author(s):  
Rebecca M. Chamberlin ◽  
Ming Tang ◽  
Rosendo Borjas Nevarez ◽  
Gordon Dennis Jarvinen ◽  
Daniel Koury ◽  
...  
Keyword(s):  
Low Temperature ◽  
Glass Waste ◽  
Waste Forms

Low-temperature fabrication of glass-based iodine waste forms via a novel preparation method

2021 ◽  
pp. 122186
Author(s):  
Biao Wu ◽  
Meng Yan ◽  
Fen Luo ◽  
Xiaoyan Shu ◽  
Yi Liu ◽  
...  
Keyword(s):  
Low Temperature ◽  
Preparation Method ◽  
Waste Forms

Analytical Electron Microscopy Study of Electron Radiation Damage in Iron Phosphate Glass Waste Forms

2002 ◽  
Vol 757 ◽  
Author(s):  
K. Sun ◽  
L. M. Wang ◽  
R. C. Ewing
Keyword(s):  
Electron Microscopy ◽  
Phosphate Glass ◽  
Analytical Electron Microscopy ◽  
Phase Segregation ◽  
Iron Phosphate ◽  
Microscopy Study ◽  
High Electron ◽  
Glass Waste ◽  
Waste Forms ◽  
Analytical Electron

ABSTRACTA series of iron phosphate glass waste forms with compositions of 45Fe2O3-55P2O5, 20Fe2O3-80P2O5, and 20Fe2O3-20Na2O-60P2O5, namely FeP-1, FeP-2 and FeP-3, was studied by analytical electron microscopy (AEM). Transmission electron microscopy (TEM) bright-field (BF) imaging showed that under the electron irradiation, phase segregation occurred in both the FeP-1 and FeP-2 samples at high electron doses (3.84×1026 e/m2). In contrast, bubbles formed in the FeP-3 sample, even at a relatively low dose (2.88×1025 e/m2), which may be attributed to the migration of Na under irradiation as in the case in sodium borosilicate glass. Series electron energy-loss spectroscopy (EELS) analysis showed that the glass materials experienced mass-loss and composition variation. No obvious Fe valence state changes under irradiation were observed within the irradiation period.

EXAFS/XANES studies of plutonium-loaded sodalite/glass waste forms

2001 ◽  
Vol 297 (3) ◽  
pp. 303-312 ◽  
Author(s):  
Michael K. Richmann ◽  
Donald T. Reed ◽  
A.Jeremy Kropf ◽  
Scott B. Aase ◽  
Michele A. Lewis
Keyword(s):  
Glass Waste ◽  
Waste Forms

scholarly journals Low Temperature Glass Sintering Based on Silico Sodium Resins

2020 ◽  
Author(s):  
María Paz Sáez-Pérez ◽  
Alberto Martínez-Ramírez ◽  
Orge Alberto DuránSuárez ◽  
María Ángeles Villegas-Broncano
Keyword(s):  
Low Temperature ◽  
Substantial Reduction ◽  
Ethyl Silicate ◽  
Lower Percentage ◽  
Mechanical Resistance ◽  
Glass Waste ◽  
Percentage Volume ◽  
The Matrix ◽  
Heating Treatment ◽  
Glass Recycling

By using silicate inorganic binders and glass waste it is possible to mould technical and artistic elements which later can be compacted by means of low temperature, and subsequently apply the sintering through high-temperature processing, which is generally lower than current melting glass processes, close to 1250 °C. The experimental phase established thermal ranges from 600°C to 750°C, a fact that allows for an effective sintering temperature (of around 650°C/18 hours). The mixtures and proportions for this experiment were fixed including ethyl silicate as a fluidizer in mixtures,as well as the size of glass grains.The results indicate good compaction of the samples after the initial phase (80°C/24h), allowing proper handling without alterations in samples edges.During heating treatment, mechanical resistance increases gradually (600-750°C), although the volume of porosity was inversely proportional. According to the matrix vs grain size relationship, the partial fusion of both materials is evident in the rounding of the glass grains as well as the resin bonds joined between them. The resins appeared in a homogenous fashion, covering and gluing the grains, a development which improves the joining of sintered samples. Samples with a mixture of sodium silicate and ethyl silicate resins experienced less melting between grains due to a lower volume of fluxing elements, which means a lower percentage volume of sodium (Na). This study concludes that a sintering process for new vitreous composites could be carried out between 650°C and 700°C, offering the opportunity for a substantial reduction in the amount of energy required to produce industrial glass. Keywords: Water-glass, glass recycling, low temperature

scholarly journals The role of Th-U minerals in assessing the performance of nuclear waste forms

2014 ◽  
Vol 78 (5) ◽  
pp. 1071-1095 ◽  
Author(s):  
G. R. Lumpkin ◽  
Yan Gao ◽  
R. Gieré ◽  
C. T. Williams ◽  
A. N. Mariano ◽  
...  
Keyword(s):  
Radiation Damage ◽  
Nuclear Waste ◽  
Low Temperatures ◽  
Elevated Temperatures ◽  
Glass Ceramics ◽  
Hydrothermal Systems ◽  
Fluid Composition ◽  
Geological Time ◽  
Glass Waste ◽  
Waste Forms

AbstractMaterials designed for nuclear waste disposal include a range of ceramics, glass ceramics and glass waste forms. Those with crystalline phases have provided the momentum for studies of minerals as a means to understand aspects of waste-form crystal chemistry, behaviour in aqueous systems and radiation damage over geological periods of time. Although the utility of natural analogue studies varies, depending upon the degree of analogy to the proposed geological repository and other factors such as chemical composition, the available data suggest that Th-U host phases such as brannerite, monazite, pyrochlore, zircon and zirconolite are resistant generally to dissolution in aqueous fluids at low temperatures. Geochemical durability may or may not extend to hydrothermal systems depending on the specifics of fluid composition, temperature and pressure. At elevated temperatures, for example, davidite may break down to new phase assemblages including titanite, ilmenite and rutile. Perovskite is generally less resistant to dissolution at low temperatures and breaks down to TiO2, releasing A-site cations to the aqueous fluid. Studies of radiation damage indicate that the oxide and silicate phases become amorphous as a result of the gradual accumulation of alpha-recoil collision cascades. Monazite tends to remain crystalline on geological time scales, a very attractive property that potentially eliminates major changes in physical properties such as density and volume, thereby reducing the potential for cracking, which is a major concern for zircon. In spite of recent success in describing the behaviour of Th-U minerals in geological systems, considerable work remains in order to understand the P-T-X conditions during alteration and T-t history of the host rocks.

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