scholarly journals Summary Report: Glass-Ceramic Waste Forms for Combined Fission Products

2011 ◽  
Author(s):  
Jarrod V. Crum ◽  
Brian J. Riley ◽  
Laura A. Turo ◽  
Ming Tang ◽  
Anna Kossoy
Keyword(s):  
Glass Ceramic ◽  
Fission Products ◽  
Summary Report ◽  
Ceramic Waste ◽  
Waste Forms

scholarly journals Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

2010 ◽  
Author(s):  
Jarrod V. Crum ◽  
Laura A. Turo ◽  
Brian J. Riley ◽  
Ming Tang ◽  
Anna Kossoy ◽  
...  
Keyword(s):  
Glass Ceramic ◽  
Fission Products ◽  
Waste Streams ◽  
Ceramic Waste ◽  
Waste Forms

Yttrium Substitution in MTiO3 (M=Ca, Sr, Ba and Ca+Sr+Ba) Perovskites and Implication for Incorporation of Fission Products into Ceramic Waste Forms

2011 ◽  
Vol 94 (9) ◽  
pp. 3112-3116 ◽  
Author(s):  
Nissim U. Navi ◽  
Giora Kimmel ◽  
Jacob Zabicky ◽  
Sergey V. Ushakov ◽  
Roni Z. Shneck ◽  
...  
Keyword(s):  
Fission Products ◽  
Ceramic Waste ◽  
Waste Forms

Cold crucible induction melter studies for making glass ceramic waste forms: A feasibility assessment

2014 ◽  
Vol 444 (1-3) ◽  
pp. 481-492 ◽  
Author(s):  
Jarrod Crum ◽  
Vince Maio ◽  
John McCloy ◽  
Clark Scott ◽  
Brian Riley ◽  
...  
Keyword(s):  
Glass Ceramic ◽  
Cold Crucible ◽  
Ceramic Waste ◽  
Feasibility Assessment ◽  
Waste Forms

scholarly journals Glass structure and crystallization in boro-alumino-silicate glasses containing rare earth and transition metal cations: a US-UK collaborative program

MRS Advances ◽  
2019 ◽  
Vol 4 (17-18) ◽  
pp. 1029-1043 ◽  
Author(s):  
John S. McCloy ◽  
José Marcial ◽  
Deepak Patil ◽  
Muad Saleh ◽  
Mostafa Ahmadzadeh ◽  
...  
Keyword(s):  
Electron Microscopy ◽  
Rare Earth ◽  
Rare Earths ◽  
Glass Ceramic ◽  
Photoelectron Spectroscopy ◽  
Alkaline Earth ◽  
Glass Structure ◽  
X Ray ◽  
Ceramic Waste ◽  
Waste Forms

ABSTRACTNuclear wastes generated from reprocessing of used nuclear fuel tend to contain a large fraction of rare earth (RE, e.g., Nd3+), transition (TM, e.g., Mo6+, Zr4+), alkali (A, e.g., Cs+), and alkaline earth cations (AE, e.g., Ba2+, Sr2+). Various strategies have been considered for immobilizing such waste streams, varying from nominally crystal-free glass to glass-ceramic to multi-phase ceramic waste forms. For glass and glass-ceramic waste forms, the added glass-forming system is generally alkali-alkaline earth-aluminoborosilicate (i.e., Na-Ca-Al-B-Si oxide). In a US-UK collaborative project, summarized here, we investigated the glass structure and crystallization dependence on compositional changes in simulated nuclear waste glasses and glass-ceramics. Compositions ranged in complexity from five – to – eight oxides. Specifically, the roles of Mo and rare earths are investigated, since a proposed glass-ceramic waste form contains crystalline phases such as powellite [(AE,A,RE)MoO4] and oxyapatite [(RE,AE,A)10Si6O26], and the precipitation of molybdenum phases is known to be affected by the rare earth concentration in the glass. Additionally, the effects of other chemical additions have been systematically investigated, including Zr, Ru, P, and Ti. A series of studies were also undertaken to ascertain the effect of the RE size on glass structure and on partitioning to crystal phases, investigating similarities and differences in glasses containing single RE oxides of Sc, Y, La, Ce, Nd, Sm, Er, Yb, or Lu. Finally, the effect of charge compensation was investigated by considering not only the commonly assessed peralkaline glass but also metaluminous and peraluminous compositions. Glass structure and crystallization studies were conducted by spectroscopic methods (i.e., Raman, X-ray absorption, nuclear magnetic resonance (NMR), optical absorption, photoluminescence, photoluminescence excitation, X-ray photoelectron spectroscopy), microscopy (i.e., scanning electron microscopy, transmission electron microscopy, electron probe microanalysis), scattering (i.e., X-ray and neutron diffraction, small angle measurements), and physical characterization (i.e., differential thermal analysis, liquidus, viscosity, density). This paper will give an overview of the research program and some example unpublished results on glass-ceramic crystallization kinetics, microstructure, and Raman spectra, as well as some examples of the effects of rare earths on the absorption, luminescence, and NMR spectra of starting glasses. The formal collaboration described here has resulted in the generation of a large number of results, some of which are still in the process of being published as separate studies.

Titanium-doped iron phosphate based glass ceramic waste forms containing 50 wt% simulated nuclear waste

2020 ◽  
Vol 239 ◽  
pp. 122314 ◽  
Author(s):  
Fu Wang ◽  
Mingwei Lu ◽  
Qilong Liao ◽  
Yuanlin Wang ◽  
Hanzhen Zhu ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Glass Ceramic ◽  
Iron Phosphate ◽  
Ceramic Waste ◽  
Waste Forms

Use of Similarity Analysis on Experiments of Different Size to Predict Critical Cooling Rates for Large Ceramic Waste Forms

2008 ◽  
Author(s):  
Kenneth J. Bateman ◽  
Charles W. Solbrig
Keyword(s):  
Thermal Stress ◽  
Cooling Rate ◽  
Fission Products ◽  
Similarity Analysis ◽  
Cylindrical Shape ◽  
Analytical Prediction ◽  
Rapid Cooling ◽  
Critical Cooling Rate ◽  
Ceramic Waste ◽  
Waste Forms

Ceramic waste forms (CWF) are produced to store fission products for the long term. They are cast into cylindrical shape at high temperature (925°C). Rapid cooling of the product is desirable for product turnaround, but cooling has the potential to crack the coalesced product into many pieces due to thermal stress. This paper investigates the rapid-cooling process with a borosilicate-glass component of the CWF used as a surrogate. The critical cooling rate of formed cylinders (the rate which separates the damage from the no-damage region) has been determined. This paper extends previous experimental data and analysis to production temperature as a step in the extrapolation of the data to production CWF’s. The glass solidifies in the range of 650°C to 625°C. The previous tests (7.8-cm diameter) were all run starting from a solid (625°C or less) to provide a basis for the higher temperature cases. Thermal stress cannot build up until solidification begins to occur. The current tests (7.8 and 9.9cm diameter) were run from the liquid temperature of 925°C. A theoretical model has been developed to analyze the data. The model includes heat transfer and the stress developed from the thermal gradients. Similarity analysis based on this model is used to produce dimensionless charts which allow data of different initial temperatures and diameters to be analyzed. The new data corroborated the previous estimate of the critical cooling rate and analytical-model projection for the minimum in-furnace cooling times for two production size CWF’s that will be stored in Yucca Mountain (70 hours for the 52-cm diameter and 35 days for the 181.5-cm sizes). To further reduce these times, an analytical prediction was made which shows that the formed cylinder can be removed from a furnace at a temperature of 320°C without any danger of cracking.

Synthesis of phosphate based glass-ceramic waste forms by a melt-quenching process: The formation process

2020 ◽  
Vol 528 ◽  
pp. 151854 ◽  
Author(s):  
Li Li ◽  
Fu Wang ◽  
Qilong Liao ◽  
Yuanlin Wang ◽  
Hanzhen Zhu ◽  
...  
Keyword(s):  
Glass Ceramic ◽  
Formation Process ◽  
Melt Quenching ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Quenching Process

scholarly journals Synroc development—Past and present applications

2017 ◽  
Vol 4 ◽  
Author(s):  
Eric R. Vance ◽  
Dorji T. Chavara ◽  
Daniel J. Gregg
Keyword(s):  
Glass Ceramic ◽  
Intermediate Level ◽  
Waste Form ◽  
Spent Fuel ◽  
Process Technology ◽  
Technology Platform ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Produce Glass ◽  
Waste Loading

ABSTRACTSynroc has evolved over the last 40 years from the titanate full-ceramics developed in the late 1970s to a technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages in terms of waste loading and suppressing volatile losses.A first of a kind Synroc plant for immobilizing intermediate level waste arising from Mo-99 production is currently in detailed engineering at ANSTO.Since the year 2000, Synroc has evolved from the titanate full-ceramics developed in the late 1970s to a technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages in terms of waste loading and suppressing volatile losses. Furthermore recent efforts have focused strongly on waste form development for plutonium-bearing wastes in the UK, for different options for the immobilization of Idaho calcines and most recently developing an engineered waste form for the intermediate level wastes arising from 99Mo production, for the Australian Nuclear Science and Technology Organisation (ANSTO). A variety of other studies are currently in progress, including engineered waste forms for spent fuel and investigating the proliferation risks for titanate-based waste forms containing highly enriched uranium or plutonium. This paper also attempts to give some perspective on Synroc waste forms and process technology development in the nuclear waste management industry.

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