Advances in Materials Science for Environmental and Energy Technologies IV

This proceedings contains a collection of 20 papers from the following five 2014 Materials Science and Technology (MS&T'14) symposia:

• Materials Issues in Nuclear Waste Management in the 21st Century
• Green Technologies for Materials Manufacturing and Processing V
• Nanotechnology for Energy, Healthcare and Industry
• Materials for Processes for CO2 Capture, Conversion, and Sequestration
• Materials Development for Nuclear Applications and Extreme Environments

• Language: English
• Publisher: Wiley
• Release date: Oct 1, 2015
• ISBN: 9781119190226

Book preview

Advances in Materials Science

for Environmental and

Energy Technologies IV

Ceramic Transactions, Volume 253

Edited by

Josef Matyáš

Tatsuki Ohji

Gary Pickrell

Winnie Wong-Ng

Raghunath Kanakala

Wiley Logo

Copyright © 2015 by The American Ceramic Society. All rights reserved.

Published by John Wiley & Sons, Inc., Hoboken, New Jersey.

Published simultaneously in Canada.

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Library of Congress Cataloging-in-Publication Data is available.

ISBN: 978-1-119-19025-7

ISSN: 1042-1122

Contents

PREFACE

MATERIALS ISSUES IN NUCLEAR WASTE MANAGEMENT

UPTAKE OF URANIUM BY TUNGSTIC ACID

ABSTRACT

INTRODUCTION

EXPERIMENTAL

RESULTS AND DISCUSSION

CONCLUSIONS

REFERENCES

ELECTRICAL CONDUCTIVITY METHOD FOR MONITORING ACCUMULATION OF CRYSTALS

ABSTRACT

INTRODUCTION

MATERIALS AND METHODS

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENTS

REFERENCES

CRYSTALLIZATION IN HIGH LEVEL WASTE (HLW) GLASS MELTERS: SAVANNAH RIVER SITE OPERATIONAL EXPERIENCE

ABSTRACT

INTRODUCTION

HISTORICAL OVERVIEW

DWPF MELTER 2 OPERATING DATA

SUMMARY

FOOTNOTES

REFERENCES

SCOPING MELTING STUDIES OF HIGH ALUMINA WASTE GLASS COMPOSITIONS

ABSTRACT

INTRODUCTION

EXPERIMENTAL APPROACH

RESULTS

DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENTS

REFERENCES

RESEARCH-SCALE MELTER: AN EXPERIMENTAL PLATFORM FOR EVALUATING CRYSTAL ACCUMULATION IN HIGH-LEVEL WASTE GLASSES

ABSTRACT

INTRODUCTION

MATERIALS

METHODS

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENTS

REFERENCES

CHARACTERIZATION OF HIGH LEVEL NUCLEAR WASTE GLASS SAMPLES FOLLOWING EXTENDED MELTER IDLING

ABSTRACT

INTRODUCTION

MELTER GLASS SAMPLING

MELTER CONDITIONS DURING IDLING

MELTER GLASS CHARACTERIZATION

DISCUSSION AND CONCLUSIONS

REFERENCES

SYNTHESIS OF MINERAL MATRICES BASED ON ENRICHED ZIRCONIUM PYROCHLORE FOR IMMOBILIZATION OF ACTINIDE-CONTAINING WASTE

ABSTRACT

INTRODUCTION

EXPERIMENTAL PROCEDURE

RESULTS AND DISCUSSION

CONCLUSION

REFERENCES

CORROSION EVALUATION OF MELTER MATERIALS FOR RADIOACTIVE WASTE VITRIFICATION

ABSTRACT

INTRODUCTION

DWPF MELTER DESIGN OVERVIEW

SCALED MELTER TESTING

DETERMINATION OF MELTER LIFETIME

CONCLUSION

REFERENCES

GREEN TECHNOLOGIES FOR MATERIALS MANUFACTURING AND PROCESSING

GREEN FLAME RETARDANT BASED ON A CERAMIC PRECURSOR

ABSTRACT

INTRODUCTION

EXPERIMENTAL

RESULTS AND DISCUSSION

CONCLUSION

ACKNOWLEDGEMENT

REFERENCES

SINGLE-SOURCE PRECURSOR APPROACH TO BARIUM DIMOLYBDATE

ABSTRACT

INTRODUCTION

EXPERIMENTAL

RESULTS AND DISCUSSION

CONCLUSION

ACKNOWLEDGEMENTS

REFERENCES

EFFECTS ON BIOMASS CHAR ADDITION ON COMBUSTION PROCESS OF PULVERIZED COAL

ABSTRACT

INTRODUCTION

EXPERIMENT

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENTS

REFERENCES

A COMPARATIVE ANALYSIS FOR CHARPY IMPACT ENERGY IN POLYESTER COMPOSITES REINFORCED WITH MALVA, RAMIE AND CURAUA FIBERS

ABSTRACT

INTRODUCTION

XPERIMENTAL PROCEDURE

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENTS

REFERENCES

RESEARCH ON SIMULTANEOUS INJECTION OF WASTE TIRES WITH PULVERIZED COAL FOR BLAST FURNACE

ABSTRACT

INTRODUCTION

RESEARCH OF THE BASIC PERFORMANCE OF COAL

RESEARCH OF THE WASTE TIRE

FEASIBILITY ANALYSIS OF INJECTING COAL MIXING WITH WASTE TIRES

CONCLUSIONS

ACKNOWLEDGEMENT

REFERENCES

RESEARCH ON USING BLAST FURNACE SLAG TO PRODUCE BUILDING STONE

ABSTRACT

INTRODUCTION

EXPERIMENTAL

CHARACTERIZATION

RESULTS AND DISCUSSION

DISCUSSION OF THE EFFECT OF COOLING CONDITION

CONCLUSION

ACKNOWLEDGEMENT

REFERENCES

A GREEN LEACHING METHOD OF DECOMPOSING SYNTHETIC CaWO4 BY HCI-H3PO4 IN TUNGSTEN PRODUCING PROCESS

ABSTRACT

INTRODUCTION

EXPERIMENT

RESULTS AND DISCUSSION

CONCLUSIONS

REFERENCES

NANOTECHNOLOGY FOR ENERGY, HEALTHCARE AND INDUSTRY

SYNTHESIS OF COATED NANO CALCIUM CARBONATE PARTICLES AND THEIR CHARACTERIZATION

ABSTRACT

INTRODUCTION

EXPERIMENTAL

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENT

REFERENCES

SYNTHESIS OF TiO2 NANOSTRUCTURES VIA HYDROTHERMAL METHOD

ABSTRACT

INTRODUCTION

EXPERIMENTAL

RESULTS AND DISCUSSION

CONCLUSION

ACKNOWLEDGEMENT

REFERENCES

CARBON NANOTUBE-BASED IMPEDIMETRIC BIOSENSORS FOR BONE MARKER DETECTION

ABSTRACT

INTRODUCTION

METHODOLOGY

RESULTS & DISCUSSION

CONCLUSION

ACKNOWLEDGEMENTS:

REFERENCES

MATERIALS AND PROCESSES FOR CO2 CAPTURE, CONVERSION, AND SEQUESTRATION

HIGH CO2 PERMEATION FLUX ENABLED BY AL2O3MODIFIER AND IN-SITU INFILTRATION OF MOLTEN CARBONATE INTO GD-DOPED CEO2 AS A CO2 SEPARATION MEMBRANE

ABSTRACT

INTRODUCTION

EXPRIMENTAL

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGEMENT

REFERENCES

MATERIALS DEVELOPMENT FOR NUCLEAR APPLICATIONS AND EXTREME ENVIRONMENTS

SUPERPLASTICITY IN CERAMICS AT HIGH TEMPERATURE

ABSTRACT

1. INTRODUCTION

2. MICROSTRUCTURAL DESIGNS FOR ACHIEVING HIGH STRAIN RATE SUPERPLASTICITY

3. SUPERPLASTIC CERAMICS AND CERAMIC COMPOSITES

4. CONCLUSION

REFERENCES:

AUTHOR INDEX

EULA

List of Tables

UPTAKE OF URANIUM BY TUNGSTIC ACID

Table 1

Table 2

Table 3

ELECTRICAL CONDUCTIVITY METHOD FOR MONITORING ACCUMULATION OF CRYSTALS

Table 1

Table 2

CRYSTALLIZATION IN HIGH LEVEL WASTE (HLW) GLASS MELTERS: SAVANNAH RIVER SITE OPERATIONAL EXPERIENCE

Table I

SCOPING MELTING STUDIES OF HIGH ALUMINA WASTE GLASS COMPOSITIONS

Table I

Table II

RESEARCH-SCALE MELTER: AN EXPERIMENTAL PLATFORM FOR EVALUATING CRYSTAL ACCUMULATION IN HIGH-LEVEL WASTE GLASSES

Table 1

Table 2

Table 3

CHARACTERIZATION OF HIGH LEVEL NUCLEAR WASTE GLASS SAMPLES FOLLOWING EXTENDED MELTER IDLING

Table 1

SYNTHESIS OF MINERAL MATRICES BASED ON ENRICHED ZIRCONIUM PYROCHLORE FOR IMMOBILIZATION OF ACTINIDE-CONTAINING WASTE

Table I

CORROSION EVALUATION OF MELTER MATERIALS FOR RADIOACTIVE WASTE VITRIFICATION

Table 1

Table 2

GREEN FLAME RETARDANT BASED ON A CERAMIC PRECURSOR

Table I.

Table II.

SINGLE-SOURCE PRECURSOR APPROACH TO BARIUM DIMOLYBDATE

Table 1.

Table 2.

EFFECTS ON BIOMASS CHAR ADDITION ON COMBUSTION PROCESS OF PULVERIZED COAL

Table I.

Table II.

Table III.

Table IV.

Table V.

A COMPARATIVE ANALYSIS FOR CHARPY IMPACT ENERGY IN POLYESTER COMPOSITES REINFORCED WITH MALVA, RAMIE AND CURAUA FIBERS

Table I

RESEARCH ON SIMULTANEOUS INJECTION OF WASTE TIRES WITH PULVERIZED COAL FOR BLAST FURNACE

Table I.

Table II.

Table III:

Table IV:

Table V:

Table VI:

Table VII:

Table VII:

RESEARCH ON USING BLAST FURNACE SLAG TO PRODUCE BUILDING STONE

Table I.

Table II.

Table III.

Table IV.

Table V.

A GREEN LEACHING METHOD OF DECOMPOSING SYNTHETIC CaWO4 BY HCI-H3PO4 IN TUNGSTEN PRODUCING PROCESS

Table I.

Table II.

SYNTHESIS OF COATED NANO CALCIUM CARBONATE PARTICLES AND THEIR CHARACTERIZATION

Table 1

Table 2

Table 3

SYNTHESIS OF TiO2 NANOSTRUCTURES VIA HYDROTHERMAL METHOD

Table 1

Table 2.

HIGH CO2 PERMEATION FLUX ENABLED BY AL2O3MODIFIER AND IN-SITU INFILTRATION OF MOLTEN CARBONATE INTO GD-DOPED CEO2 AS A CO2 SEPARATION MEMBRANE

Table 1

SUPERPLASTICITY IN CERAMICS AT HIGH TEMPERATURE

Table 1

List of Illustrations

UPTAKE OF URANIUM BY TUNGSTIC ACID

Figure 1. X-Ray Powder Diffraction Pattern for the Reaction between Tungstic Acid and Uranium Acetate, The Upper Picture Represent the Amorphous Product Isolated from the Initial Reaction.

Figure 2. XRF Spectrum of the Uranium Acetate/ Tungstic Acid Product

Figure 3. Graphical Representation of the First Order Reaction of Uranyl Ions with Excess H2WO4 (10 mmol)

Figure 4. Graphical Representation of ln[kobs] as a Function of ln[H2WO4]

Figure 5. Possible Mechanism for Uranium Uptake by Tungstic Acid

Figure 6. Green Cycle for Uranium Sorption by Tungstic Acid

ELECTRICAL CONDUCTIVITY METHOD FOR MONITORING ACCUMULATION OF CRYSTALS

Figure 1. SEM image of spinel crystals.

Figure 2. The design of the probe for conductivity measurements.

Figure 3. Data fitting with Nyquist plot.

Figure 4. Data fitting with Bode plots.

Figure 5. Equivalent circuit used for fitting the data.

Figure 6. Calculated versus theoretical conductivities and cell constants (K) obtained for each probe.

Figure 7. Accumulated layers of spinel crystals in 10 S/m standard conductivity solution. Layer thicknesses: A) 0 mm; B) 1.6 mm; C) 7.3 mm.

Figure 8. Change of conductivity with increased thickness (h) of accumulated layer in standard solutions having conductivities 10 and 20 S/m, including R² measure of goodness of fit.

Figure 9. Assembly to monitor crystal accumulation in the glass melt including a detail of electrical conductivity (EC) probe.

Figure 10. Change of conductivity of glass melt with time at 850°C.

Figure 11. SEM image of spinel crystals (light gray) accumulated at the bottom of the crucible and probe wires including a paddle at the bottom (white) and alumina sheath (dark gray) to measure the conductivity of glass (gray) as a function of time.

SCOPING MELTING STUDIES OF HIGH ALUMINA WASTE GLASS COMPOSITIONS

Figure I - Micrographs of Glass 4744

Figure II - Glass 5385 Phase Segregation

Figure III - Elemental Map of Glass 5385 Polished Cross-section

Figure IV - XRD Spectra of Glasses Containing Nepheline ( = CaF2)

Figure V - Cross-section and Micrograph of Glass 4744.1

Figure VI – Segregated salts plot

Figure VII – High crystallinity plot

RESEARCH-SCALE MELTER: AN EXPERIMENTAL PLATFORM FOR EVALUATING CRYSTAL ACCUMULATION IN HIGH-LEVEL WASTE GLASSES

Figure 1. Research-scale melter.

Figure 2. Temperature profile in the glass-discharge riser during the first idling.

Figure 3. Cross-section of the RSM after the test.

Figure 4. SEM image of the layer (12 × 7 mm section from Figure 3) accumulated over three idling periods: I - first idling, II - second idling, III - third idling.

Figure 5. SEM images of the accumulated layers for Ni 1.5/Fe17.5 (I) and Ni1.5 (II) glass (double crucible test, 850°C for 7 days).⁸

Figure 6. Layer thickness as a function of time for Ni1.5/Fe17.5, Ni1.5, and Ni1.29 glasses (double crucible test, 850°C).⁸

Figure 7. Concentrations of spinel in poured glass samples collected at different times after first and second idling.

CHARACTERIZATION OF HIGH LEVEL NUCLEAR WASTE GLASS SAMPLES FOLLOWING EXTENDED MELTER IDLING

Figure 1. Cross-sectional Overview of the DWPF Melter.

Figure 2. Detail of collection of first glass sample after three month outage.

Figure 3. Detail of collection of second glass sample after three month outage.

Figure 4. Overview of melter, riser, and vapor space temperatures and heater power during three month outage.

Figure 5. BSE Micrograph and EDS Spectra of a Spinel Crystal Observed in Glass PC0126.

Figure 6. BSE Micrograph and EDS Spectrum of a Noble Metal Crystal Observed in Glass PC0126.

SYNTHESIS OF MINERAL MATRICES BASED ON ENRICHED ZIRCONIUM PYROCHLORE FOR IMMOBILIZATION OF ACTINIDE-CONTAINING WASTE

Figure 1. Results of thermodynamic calculations when using different oxides for synthesis of the composition No 2

Figure 2. Data of thermodynamic calculation of the process for synthesis of various charge compositions

Figure 3. Diffractograms of ceramics for various charge compositions (HAW content is 10 %)

Figure 4. Microstructure and composition (atomic %) of products produced from the compositions No 2 (a) and No 3 (b) with HAW content equal to 10 %

Figure 5. Diffractograms of products produced from the composition No 2 with various quantities of HAW

Figure 6. Microstructure and composition (atomic %) of the product produced from the composition No 2 with HAW content equal to 10 %

Figure 7. Diffractogram of the product produced from the corrected composition

CORROSION EVALUATION OF MELTER MATERIALS FOR RADIOACTIVE WASTE VITRIFICATION

Figure 1. Cross-sectional view of DWPF Melter (prior to addition of bubblers).²

Figure 2. DWPF Melter Refractory.²

GREEN FLAME RETARDANT BASED ON A CERAMIC PRECURSOR

Figure 1. Structure of D-gluconic acid (left) and Metal gluconates (right) where M=Ca, Zn, Cu

Figure 2. Structure of Calcium Molybdenyl Gluconate

Figure 3. Setting for ASTM D 3801 Flame Test / UL-94 Vertical Test

Figure 4. Infrared spectrum of calcium molybdenyl gluconate.

Figure 5. Thermogravimetric curves of pure calcium molybdenyl gluconate, polyurethane foam treated with calcium molybdenyl gluconate (loading 2.89 lb/ft³) and untreated foam.

Figure 6. XRD pattern of pyrolysis product derived from calcium molybdenyl gluconate

Figure 7. SEM image of pyrolysis product derived from calcium molybdenyl gluconate

SINGLE-SOURCE PRECURSOR APPROACH TO BARIUM DIMOLYBDATE

Figure 1. Benzilate Structures (A) Benzilate Anion (B) Expected Product Anion and (C) Actual Product Anion Complex

Figure 2. Thermal Ellipsoid Plot of Structure

Figure 3. Packing Diagram

Figure 4. TGA Trace of the BaMo2O7 Precursor.

Figure 5. XRD Pattern for BaMo2O7 Derived from the Precursor at 450°C. Grey bars are the ICDD PDF File # 00-034-1206 for BaMo2O7.

EFFECTS ON BIOMASS CHAR ADDITION ON COMBUSTION PROCESS OF PULVERIZED COAL

Figure 1. TG curves of different additive amount of biomass char at a heating rate of 20 K/min

Figure 2. DTG curves of different additive amount of biomass char at a heating rate of 20 K/min

Figure 3. Relation between Ti and TF with different additive amount of biomass char for blending coal

Figure 4. Relation between combustion indexes with different additive amount of biomass char for blending coal

A COMPARATIVE ANALYSIS FOR CHARPY IMPACT ENERGY IN POLYESTER COMPOSITES REINFORCED WITH MALVA, RAMIE AND CURAUA FIBERS

Figure 1. (a) Malva plant, (b) Ramie plant and (c) Curaua Plant.

Figure 2. (a) Malva fiber, (b)Curaua fiber and (c) Ramie fiber.

Figure 3. Charpy impact energy as a function of the amount of fibers.

Figure 4. Fracture surface of the specimen pure polyester (0%· fiber): (A) general view with low increase (B) higher increase.

Figure 5. Fracture surface of the specimen 30% malva fiber/polyester composite (A) general view with low increase (B) higher increase.

RESEARCH ON SIMULTANEOUS INJECTION OF WASTE TIRES WITH PULVERIZED COAL FOR BLAST FURNACE

Figure 1. The feature of original inner tube(a), fine particle(b) and large particle(c) after grinding

Figure 2. The feature of original cover tire(a) and particle after grinding(b)

Figure 3. The combustion ratio of the nine kinds of coal in different temperature

Figure 4. Calorific value of different coal and the mixture of coal and waste tire

RESEARCH ON USING BLAST FURNACE SLAG TO PRODUCE BUILDING STONE

Figure 1. Samples with different amount of SiO2 (a)-Sl, (b)-S2, (c)-S3, (d)-S4

Figure 2. Samples with different metallic oxides addition (a)-Fl, (b)-F2, (c)-Cl, (d)-C2

Figure 3. Samples obtained under different cooling condition (a)-Ll, (b)-K2, (c)-L2, (d)-K2

Figure 4. XRD analysis for the sample L1(light-color region) and L2

Figure 5. XRD analysis for the light-color region and dark-color region in the sample L1

Figure 6. BEI observation and microchemical analysis for sample L1

A GREEN LEACHING METHOD OF DECOMPOSING SYNTHETIC CaWO4 BY HCI-H3PO4 IN TUNGSTEN PRODUCING PROCESS

Figure 1. XRD spectra of synthetic scheelite

Figure 2a. SEM image of synthetic scheelite

Figure 2b. SEM image and EDS analysis of synthetic scheelite

Figure 3. Leaching rate diagrams of tungsten with different (a) stirrer intensity, (b) W/P mole ratio, (c) HCl concentration and (d) temperature

Figure 4. diagrams of l-(l-x) to time with different (a) HCl concentration and (b) temperature

Figure 5. diagram of lnk to 1/T

SYNTHESIS OF COATED NANO CALCIUM CARBONATE PARTICLES AND THEIR CHARACTERIZATION

Fig. 1. TGA analysis of uncoated CaCO3

Fig. 2. TGA analysis of SAC-CaCO3

Figure 4. Scanning Electron Micrographs of Different Samples CaCO3 particles

Figure 5. Scanning Electron Micrographs of SAC-CaC03 particles

SYNTHESIS OF TiO2 NANOSTRUCTURES VIA HYDROTHERMAL METHOD

Figure 1. X-Ray pattern of the synthesized 1-D structures

Figure 2. EDX analysis of synthesized 1 D nanostructures

Figure 3. SEM images of the powders synthesized (a) at 130 °C for 12 h (started to diverge nanosheets from amorphous powder) (b) at 130 °C for 12 h (diverged nanosheets from amorhous powder) (c) at 130 °C for 36 h (nanotubes from P25) (d) at 130 °C for 36 h (nanowires from amorphous powder)

Figure 4. Rate constant versus time graph of the powders.

CARBON NANOTUBE-BASED IMPEDIMETRIC BIOSENSORS FOR BONE MARKER DETECTION

Figure 1. Nyquist plots showing the charge transfer resistance of the bare gold electrode and the increase in charge transfer resistance with immobilization of avidin and biotinylated c-terminal telopeptide antibody.

Figure 2. Equivalent circuit model fitted to Nyquist plots.

Figure 3. Nyquist plots showing increase in charge transfer resistance with increase in concentration of c-terminal telopeptide.

Figure 4. Calibration curve showing percent change in charge transfer resistance against increase in concentration of c-terminal telopeptide.

Figure 5. Calibration curve showing percent change in absolute impedance against increase in concentration of c-terminal telopeptide at f=18.75 Hz.

Figure 6. Calibration curve showing percent change in absolute impedance against increase in concentration of c-terminal telopeptide at f=18.75 Hz with interference introduced by DMEM and FBS.

HIGH CO2 PERMEATION FLUX ENABLED BY AL2O3MODIFIER AND IN-SITU INFILTRATION OF MOLTEN CARBONATE INTO GD-DOPED CEO2 AS A CO2 SEPARATION MEMBRANE

Fig. 1 Schematic of permeation cell with in-situ MC infiltration setup

Fig. 2 Microstructures of (a) porous GDC-AL2O3 matrix; (b) GDC-Al2O3 MOCC membrane; (c) porous GDC matrix; (d) GDC-Al2O3 MOCC.

Fig. 3 CO2 flux density as a function of logarithm of CO2partial pressure for Al2O3-modified MOCC membrane

Fig. 4 CO2 Flux Density of GDC-MOCC as a function of temperature

Fig. 5 Long-term stability of CO2 and O2 flux densities of GDC-Al2O3 MOCC

Fig. 6 Microstructures of MOCC membrane after running 100-hour; (a) feeding side of GDC-Al2O3 MOCC; (b) sweeping side of GDC-Al2O3 MOCC; (c) cross-section in the mid-section of GDC-Al2O3 MOCC; (d) cross-section in the mid-section of GDC-MOCC.

SUPERPLASTICITY IN CERAMICS AT HIGH TEMPERATURE

Figure 1: Phase diagram of zirconia-yttria system [adapted from 31].

Figure 2: Tensile specimens of 3Y-TZP doped with 0.20 wt% alumina before and after tensile deformation [32].

Figure 3. ensile elongation of Si3N4 ceramics at high temperature [35].

Preface

The Materials Science and Technology 2014 Conference and Exhibition (MS&T'14) was held October 12‒16, 2014 at the David L. Lawrence Convention Center, Pittsburgh, Pennsylvania. One of the major themes of the conference was Environmental and Energy Issues. Twenty papers from five symposia are included in this volume. These symposia included Materials Issues in Nuclear Waste Management in the 21st Century; Green Technologies for Materials Manufacturing and Processing VI; Nanotechnology for Energy, Healthcare and Industry; Materials and Processes for CO2 Capture, Conversion, and Sequestration; and Materials Development for Nuclear Applications and Extreme Environments.

The success of these symposia and the publication of the proceedings could not have been possible without the support of The American Ceramic Society and other organizers of the program. The program organizers for the above symposia are appreciated. Their assistance, along with that of the session chairs, was invaluable in ensuring the creation of this volume.

JOSEFMATYÁŠ, Pacific Northwest National Laboratory, USA

TATSUKI OHJI, AIST, JAPAN

GARY PICKRELL, Virginia Polytechnic Institute and State University, USA

WINNIEWONG-NG, NIST, USA

RAGHUNATHKANAKALA, University of Idaho, USA

Materials Issues in Nuclear Waste Management

UPTAKE OF URANIUM BY TUNGSTIC ACID

Hamed Albusaidi, Cory K. Perkins, and Allen W. Apblett

Oklahoma State University Stillwater, OK, USA

ABSTRACT

Nuclear energy is undergoing a renaissance because it does not contribute to global warming. However, even ignoring the issue of radioactive waste, the production of nuclear energy has its own environmental impacts. The mining and refining of uranium produces tailings that slowly leach uranium and other toxic metals into aquifers. Military use of depleted uranium also releases materials that can contaminate aquifers and drinking water supplies. However, the more common route for human ingestion of uranium is from natural waters in contact with uranium-rich granitoids. Uranium is a health risk due to its heavy metal character that leads to damage to the kidneys. Therefore, there is a strong need for processes to prevent contamination of aquifers and purification of drinking water supplied. Tungstic acid was found to uptake uranium from water with a very high capacity of 1.90 moles U per mole of H2WO4 (181% by weight). The sorption process produces an amorphous hydrated uranium tungstate phase and is first order in uranyl ions and second order in tungstic acid. An attractive feature of this process is the ease by which the uranium can be isolated and the sorbent, H2WO4, can be regenerated for reuse. It is also effective for other metals that are of more interest to the petrochemical and coal industry such as cadmium and lead.

INTRODUCTION

Uranium is a common contaminant of ground water and can arise from natural and anthropogenic sources. Uranium occurs naturally in the earth's crust and in surface and ground water and can dissolve over a wide pH range when bedrock containing uranium-rich granitoids and granites comes in contact with soft, slightly alkaline bicarbonate waters under oxidizing conditions. This is a common occurrence throughout the world with perhaps the worst place being in Finland where exceptionally high uranium concentrations, up to 12,000 ppb, are found in wells drilled in bedrock.¹ In Canada, concentrations of uranium up to 700 ppb have been found in private wells² while some sites in the United States have serious contamination with uranium. For example, in the Simpsonville-Greenville area of South Carolina, high amounts of uranium (30 to 9900 ppb) were found in 31 drinking water wells.³ This is believed to be the result of veins of pegmatite that occur in the area. Besides entering drinking water from naturally occurring deposits, uranium can also contaminate the water supply as the result of human activity, such as mill tailings from uranium mining and agriculture.⁴; ⁵ Phosphate fertilizers often contain uranium at an average concentration of 150 ppm making them an appreciable contributor of uranium to groundwater.⁶ The Fry Canyon site in Utah is a good example of the dangers of uranium mine tailings. The groundwater at this site was contaminated with uranium at levels as high as 16,300 ppb with a median concentration of 840 ppb before remedial actions were taken.⁷ The corrosion and dissolution of depleted uranium armored penetrators has also been demonstrated as a source of drinking water contamination.⁸

Contrary to what might be expected, the major health effect of uranium is chemical kidney toxicity, rather than a radiation hazard,⁹ with both functional and histological damage to the proximal tubulus of the kidney occurring.¹⁰ Little is known about the effects of long-term environmental uranium exposure in humans but uranium exposure lead to increased urinary glucose, alkaline phosphatase, and ß-microglobulin excretion¹¹ as well as increased urinary albumin levels¹². As a result of such studies, the World Health Organization has proposed a guideline value of 2 ppb for uranium in drinking water while the EPA has specified a limit of 30 ppb.

Current municipal treatment practices are not effective in removing uranium but experimentation indicates that uranium removal can be accomplished by a variety of processes such as modification of pH and/or chemical treatment (e.g. alum).¹³ Several sorbents have been shown to be useful for removal of uranium from water including activated carbon, iron powder, magnetite, anion exchange resin and cation exchange resin.⁴ However, two common household treatment devices were found not to be completely effective for uranium removal³.

Besides treatment of well water, there is also a strong need for prevention of the spread of uranium contamination from concentrated sources such as uranium mine tailings. Commonly used aboveground water