scholarly journals Corrosion of inconel in high-temperature borosilicate glass melts containing simulant nuclear waste

2017 ◽  
Author(s):  
Xianhe Mao ◽  
Xiaoning Yuan ◽  
Clive T. Brigden ◽  
Jun Tao ◽  
Neil C. Hyatt ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Glass Melts

Nitrogen and Argon in Borosilicate Glass: Solubility, Diffusivity, Residual Gas Concentration and Behaviour of Bubbles in Glass Melts, Containing Both Gases

2008 ◽  
Vol 39-40 ◽  
pp. 437-442 ◽  
Author(s):  
Detlef Köpsel ◽  
Markus Booβ ◽  
M. Opyd ◽  
Maria Louisa Aigner
Keyword(s):  
High Temperature ◽  
Gas Exchange ◽  
Borosilicate Glass ◽  
Diffusion Coefficients ◽  
Molten Glass ◽  
Extraction Method ◽  
Vacuum Extraction ◽  
Glass Melts ◽  
Gas Concentration ◽  
Residual Gas

Diffusivities of nitrogen and argon in a borosilicate glass were determined with two different methods: (1) from gas exchange experiments between molten glass and bubbles containing nitrogen and argon, and (2) from solution rates of nitrogen and argon in glass during saturation experiments. Between 1200°C and 1580°C the diffusion coefficients of nitrogen and argon yielded the following equations:      − = − RT s m DN 134900 exp 10 22 . 1 ] / [ 6 . 2 2 and      − = − RT s m DAr 125300 exp 10 08 . 1 ] / [ 6 . 2 , with R=8.314 J/(mol.K). The solubilities and residual gas concentration in the glass which are necessary for the calculation of the diffusivities were determined with the high temperature vacuum extraction method.

The Use of Hot-Isostatic Pressing to Process Nuclear Waste Forms

2009 ◽  
Author(s):  
Martin W. A. Stewart ◽  
Sam A. Moricca ◽  
Tina Eddowes ◽  
Yingjie Zhang ◽  
Eric R. Vance ◽  
...  
Keyword(s):  
Electrical Conductivity ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Hot Isostatic Pressing ◽  
Processing Technology ◽  
Nuclear Wastes ◽  
Isostatic Pressing ◽  
Waste Forms ◽  
Nuclear Waste Forms ◽  
Glass Viscosity

ANSTO has developed a combination of tailored nuclear waste form chemistries coupled with the use of flexible hot-isostatic pressing processing technology to enable the successful incorporation of problematic nuclear wastes into dense, durable monoliths. This combined package also enables the design of waste forms with waste loadings well in excess of those achievable via baseline melting routes using borosilicate glass, as hot-isostatic pressing is not constrained by factors such as glass viscosity, crystallisation and electrical conductivity. In this paper we will discuss some of our experiences with problematic wastes, namely plutonium wastes, sludges and HLW such as the Idaho calcines.

An Electrodeless Melter for Vitrification of Nuclear Waste

1996 ◽  
Vol 465 ◽  
Author(s):  
J. P. Freidberg ◽  
A. J. Shajii ◽  
K. W. Wenzel ◽  
J. R. Lierzer
Keyword(s):  
High Temperature ◽  
Radioactive Waste ◽  
Nuclear Waste ◽  
Thermal Analyses ◽  
Iron Core ◽  
Leaching Rate ◽  
One Dimensional ◽  
High Silica ◽  
Waste Loading

ABSTRACTThis paper describes a new concept for a high-temperature, electrodeless melter for vitrifying radioactive wastes. Based on the principles of induction heating, it circumvents a number of difficulties associated with existing technology. The melter can operate at higher temperatures (1500–2000°C vs 1150°C), allowing for a higher quality, more durable glass which reduces the long-term leaching rate. Higher processing temperatures also enable conversion from borosilicate to high-silica glass which can accommodate 2 to 3 times as much radioactive waste, potentially halving the ultimate required long-term disposal space. Finally, with high temperatures, conversion of nuclear waste into ceramics can also be considered. This too leads to higher waste loading and the reduction of repository space. The melter is toroidal, linked by an iron core transformer that allows efficient electrical operation even at 60 Hz. One-dimensional electrical and thermal analyses are presented.

The incorporation of Li2SO4 into barium borosilicate glass for nuclear waste immobilisation

2021 ◽  
pp. 162746
Author(s):  
Rifat Farzana ◽  
Pranesh Dayal ◽  
Inna Karatchevtseva ◽  
Zaynab Aly ◽  
Daniel J. Gregg
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Barium Borosilicate Glass

Dissolution of Accumulated Spinel Crystals in Simulated Nuclear Waste Glass Melts

2018 ◽  
Vol 22 (2) ◽  
pp. 05018001 ◽  
Author(s):  
Devon L. McClane ◽  
Kevin M. Fox ◽  
Fabienne C. Johnson ◽  
Jake W. Amoroso ◽  
Albert A. Kruger
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Glass Melts ◽  
Nuclear Waste Glass

Ion Implantation Studies of Nuclear Waste Forms

1981 ◽  
Vol 6 ◽  
Author(s):  
Clyde J. M. Northrup ◽  
George W. Arnold ◽  
Thomas J. Headley
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Alpha Decay ◽  
Lead Ions ◽  
Waste Form ◽  
Elastic Recoil ◽  
Elastic Recoil Detection ◽  
Waste Forms ◽  
Basic Studies ◽  
Nuclear Waste Forms

ABSTRACTThe first observations of physical and chemical changes induced by lead implantation damage and leaching are reported for two proposed U.S. nuclear waste forms (PNL 76–68 borosilicate glass and Sandia titanate ceramics) for commercial wastes. To simulate the effects of recoil nucleii due to alpha decay, the materials were implanted with lead ions at equivalent doses up to approximately 1 × 1019 a decays/cm3 . In the titanate waste form, the zirconolite, perovskite, hollandite, and rutile phases all exhibited a mottled appearance in the transmission electron microscope (TEM) typical of defect clusters in radiation damaged, crystalline solids. One titanate phase containing uranium was found by TEM to be amorphous after implantation at the highest dose. No enhanced leaching (deionized water, room temperature, 24 hours) of the irradiated titanate waste form, including the amorphous phase, was detected by TEM, but Rutherford backscattering (RBS) suggested a loss of cesium and calcium after 21 hours of leaching. The RBS spectra also indicated enhanced leaching from the PNL 76–68 borosilicate glass after implantation with lead ions, in general agreement with the observations of Dran, et al. [6,7] on other irradiated materials. Elastic recoil detection spectroscopy (ERD), used to profile hydrogen after leaching, showed penetration of the hydrogen to several thousand angstroms for both the implanted and unimplanted materials. These basic studies identified techniques to follow the changes that occur on implantation and leaching of complex amorphous and crystalline waste forms. These studies were not designed to produce comparisons between waste forms of gross leach rates.

Natural Analogues: Their Application to the Prediction of the Long-Term Behavior of Nuclear Waste Forms

1986 ◽  
Vol 84 ◽  
Author(s):  
Rodney C. Ewing ◽  
Michael J. Jercinovic
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Large Scale ◽  
Laboratory Data ◽  
Waste Form ◽  
Long Time ◽  
Natural Analogues ◽  
Long Term Behavior ◽  
Nuclear Waste Forms

AbstractOne of the unique and scientifically most difficult aspects of nuclear waste isolation is the extrapolation ofshot-term laboratory data (hours to years) to the long time periods (103-105 years) required by regulatory agencies for performance assessment. The direct verification of these extrapolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the lay public that there is a demonstrable and reasonable basis for accepting the long-term extrapolations. Natural analogues of both the repository environment (e.g. radionuclide migration at Oklo) and nuclear waste form behavior (e.g. alteration of basaltic glasses and radiation damage in minerals) have been used to demonstrate the long-term behavior of large scale geologic systems and, on a smaller scale, waste form durability. This paper reviews the use of natural analogues to predict the long-term behavior of nuclear waste form glasses. Particular emphasis is placed on the inherent limitations of any conclusions that are based on “proof” by analogy. An example -- corrosion of borosilicate glass -- is discussed in detail with specific attention to the proper and successful use of natural analogues (basaltic glass) in understanding the long-term corrosion behavior of borosilicate glass.

Effect of Yttrium Oxide on the Viscosity and Crystallization of Borosilicate Glass at High Temperature

2013 ◽  
Vol 750-752 ◽  
pp. 974-977 ◽  
Author(s):  
Zhong Qing Tian ◽  
Yu Kai Zhu ◽  
Wei Jiu Huang
Keyword(s):  
Activation Energy ◽  
High Temperature ◽  
Borosilicate Glass ◽  
Liquidus Temperature ◽  
Content Increase ◽  
Energy Value ◽  
Maximum Activation ◽  
Gradient Furnace ◽  
Forming Temperature ◽  
The Difference

Effect of Y2O3 on the viscosity and Crystallization of of borosilicate glass at high temperature was investigated at high temperature. Melt viscosity as a function of temperature was determined by using a rotating spindle viscometer. Liquidus temperature was determined by the Gradient Furnace Method. The results show that the viscosity decreased as a function of Y2O3 content. The activation energy of glass without Y2O3 is about 110.3 kJ·mol-1 and the activation energy increases with the Y2O3 addition up to the 2 wt%. At 2 wt% Y2O3, the specimen shows the maximum activation energy value of 112.6 kJ·mol-1. As Y2O3 content increase, the activation energy decreases. The fiber-forming temperature of glass without Y2O3 is about 1342 oC and the fiber-forming temperature increases with the Y2O3 addition up to the 2 wt%. At 2 wt% Y2O3, the sample shows the maximum activation energy value of 1370 °C. When Y2O3 content increase, the fiber-forming temperature decreases. The liquidus temperature of glass decreases from 1313 °C to 1023 °C when Y2O3 content increases from 0 wt% to 6 wt%. The difference between the fiber-forming and the liquidus temperatures of glass increases from 30 oC to 336 °C when Y2O3 content increases from 0 wt% to 6 wt%.

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