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.

A Flow Model for the Kinetics of Dissolution of Nuclear Waste Forms; A Comparison of Borosilicate Glass, Synroc and High-Silica Glass

1981 ◽  
Vol 11 ◽  
Author(s):  
Pedro B. Macedo ◽  
Aaron Barkatt ◽  
Joseoph H. Simmons
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Flow Model ◽  
Release Rates ◽  
Waste Forms ◽  
High Silica ◽  
Kinetics Of Dissolution ◽  
Kinetics Of ◽  
Nuclear Waste Forms

A model has been developed to predict the long-term leach or release rates of various waste-form materials under repository conditions.

Applications of Electron Microscopy to Containment of Radio-Nuclides

1982 ◽  
Vol 40 ◽  
pp. 606-609
Author(s):  
Carol M. Jantzen
Keyword(s):  
Nuclear Waste ◽  
Fission Products ◽  
Silica Glasses ◽  
Long Term Storage ◽  
Waste Forms ◽  
High Silica ◽  
Solid Form ◽  
Reference Form ◽  
Term Storage

The long radioactive lifetime of the fission products in nuclear wastes requires that the materials be isolated from the biosphere for periods of 103 to 105 years. One method of accomplishing this is to consolidate the waste into a chemically stable solid form and to contain this within a multiple barrier canister which can be transported to a geologically stable repository for long-term storage. A number of candidate solid waste forms are being assessed to determine their suitability for incorporating various nuclear waste compositions and they include borosilicate glass (the current reference form), ceramics, high silica glasses, and cement.

Long-Term Thermomechanical and Thermohydrological Factors Controlling the Optimal Design of a Nuclear Waste Repository

1982 ◽  
Vol 15 ◽  
Author(s):  
J. S. Y. Wang ◽  
D. C. Mangold ◽  
C. F. Tsang
Keyword(s):  
Optimal Design ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Horizontal Gradient ◽  
Major Mechanism ◽  
Surface Uplift ◽  
Generic Modeling ◽  
Waste Repository ◽  
Waste Loading

ABSTRACTSurface uplift and buoyancy flow are two of the major long-term, far-field perturbations to the geologic formations around a nuclear waste repository. The allowable surface uplift has been accepted in the literature as a criterion limiting the repository waste loading density. It has also been recognized in generic modeling studies that the buoyancy distortion of the ambient groundwater flow around a repository is a major mechanism for radionuclide transport. However, the buoyancy considerations have yet to be quantified for the purpose of optimal design of a radioactive waste repository. We suggest the possibility of using the buoyancy gradient when compared with the ambient regional (horizontal) gradient as a measurable thermohydrologic factor that controls the design of waste loading. This study indicates that the buoyancy gradient could in some cases become the main controlling factor. To decrease the buoyancy effects, much lower values of waste loading density should be considered in the design of the waste repository.

Final Disposal Through Public Participation

2001 ◽  
Author(s):  
P. Van Negen
Keyword(s):  
Radioactive Waste ◽  
Public Participation ◽  
Nuclear Waste ◽  
Active Participation ◽  
Local Communities ◽  
Innovative Approach ◽  
Final Disposal ◽  
Class A

Abstract The Context: • 1998. The Belgian government selects the existing nuclear sites for the long term disposal of Class A nuclear waste. • ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and enriched Fissile Materials, adopts an innovative approach of active participation and sysematic dialogue with the local communities.

Application of Polyhexamethyleneguanidine Type Biocides at Cementing the Radioactive Waste

2001 ◽  
Author(s):  
Andrey P. Varlakov ◽  
Olga A. Gorbunova ◽  
Aleksandr S. Barinov ◽  
Vadim A. Iljin ◽  
Konstantin M. Efimov ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Compression Strength ◽  
Radiation Resistance ◽  
Water Resistance ◽  
Leaching Rate ◽  
Biocidal Activity ◽  
Wide Range ◽  
Cement Compound ◽  
Biological Corrosion

Abstract In order to prevent biological corrosion of cement compound containing radioactive waste, it is proposed to use biocidal additives of polyhexamethyleneguanidines (PHMG), which have a wide range of biocidal activity. It has been shown that inclusion of biocidal additives of polyhexamethyleneguanidines in quantities 0,25–2% wt. into the grout used for the solidification of radioactive waste (RW) or for recovering the integrity of old RW repositories provides the necessary bacteriostatic and biocidal protection of cement compound and improves all the regulated properties — compression strength, Cs-137 leaching rate, frost-resistance, radiation resistance and long term water resistance.

scholarly journals High-Temperature Nuclear Reactors (Overview. Part 1) / Augstas Temperatūras Kodolreaktori (Pārskata raksts) 1. daļa

2013 ◽  
Vol 50 (1) ◽  
pp. 47-57
Author(s):  
J. Ekmanis ◽  
E. Tomsons ◽  
N. Zeltiņš
Keyword(s):  
High Temperature ◽  
Radioactive Waste ◽  
Nuclear Reactors ◽  
Future Generation ◽  
Nuclear Material ◽  
Electricity Production ◽  
Nuclear Fuels ◽  
International Forum

At the Generation IV International Forum (GIF) of 2001 the measures were approved which are necessary for the development of future generation nuclear reactors (NRs). Six best high-temperature NR technologies were selected, with the main criteria being the safe and economically profitable operation, long-term use, protection against the employment of nuclear material for military purposes and terroristic attacks as well as technologies of fuel close cycle in order to increase the amount of fission material and decrease the amount of highly radioactive waste. In four of the technologies, apart from electricity production also hydrogen is obtained. Part 1 presents a generalized description of the high-temperature NRs, their comparative characteristics and history, with the stopped and operational HTNRs outlined. The properties of different type nuclear fuels are described in detail

Microstructural characterization of a rapidly solidified Al-Fe-V-Si alloy for elevated temperature applications

1988 ◽  
Vol 46 ◽  
pp. 550-551
Author(s):  
R. E. Franck ◽  
J. A. Hawk ◽  
G. J. Shiflet
Keyword(s):  
High Temperature ◽  
Elevated Temperature ◽  
Grain Growth ◽  
Volume Fraction ◽  
Microstructural Characterization ◽  
Second Phase ◽  
Microstructural Stability ◽  
Elevated Temperature Strength ◽  
Temperature Applications

Rapid solidification processing (RSP) is one method of producing high strength aluminum alloys for elevated temperature applications. Allied-Signal, Inc. has produced an Al-12.4 Fe-1.2 V-2.3 Si (composition in wt pct) alloy which possesses good microstructural stability up to 425°C. This alloy contains a high volume fraction (37 v/o) of fine nearly spherical, α-Al12(Fe, V)3Si dispersoids. The improved elevated temperature strength and stability of this alloy is due to the slower dispersoid coarsening rate of the silicide particles. Additionally, the high v/o of second phase particles should inhibit recrystallization and grain growth, and thus reduce any loss in strength due to long term, high temperature annealing.The focus of this research is to investigate microstructural changes induced by long term, high temperature static annealing heat-treatments. Annealing treatments for up to 1000 hours were carried out on this alloy at 500°C, 550°C and 600°C. Particle coarsening and/or recrystallization and grain growth would be accelerated in these temperature regimes.

KUBOTA KNC-03

Alloy Digest ◽  
2010 ◽  
Vol 59 (1) ◽  
Keyword(s):  
Compressive Strength ◽  
High Temperature ◽  
Physical Properties ◽  
Tensile Properties ◽  
High Strength ◽  
Temperature Performance ◽  
Resistance To Oxidation

Abstract Kubota KNC-03 is a grade with a combination of high strength and excellent resistance to oxidation. These properties make this alloy suitable for long-term service at temperature up to 1250 deg C (2282 deg F). This datasheet provides information on physical properties, hardness, elasticity, tensile properties, and compressive strength as well as creep. It also includes information on high temperature performance as well as casting and joining. Filing Code: Ni-676. Producer or source: Kubota Metal Corporation, Fahramet Division. See also Alloy Digest Ni-662, April 2008.

ATI 6-2-4-2

Alloy Digest ◽  
2020 ◽  
Vol 69 (8) ◽  
Keyword(s):  
Tensile Strength ◽  
Titanium Alloy ◽  
High Temperature ◽  
Creep Strength ◽  
High Strength ◽  
Heat Treating ◽  
Good Combination ◽  
Long Term Stability ◽  
Temperature Performance

Abstract ATI 6-2-4-2 is a near-alpha, high strength, titanium alloy that exhibits a good combination of tensile strength, creep strength, toughness, and long-term stability at temperatures up to 425 °C (800 °F). Silicon up to 0.1% frequently is added to improve the creep resistance of the alloy. This datasheet provides information on composition, physical properties, hardness, and tensile properties as well as creep. It also includes information on high temperature performance as well as forming, heat treating, machining, and joining. Filing Code: Ti-169. Producer or Source: ATI.

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