Carol Jantzen - Academia.edu (original) (raw)

Papers by Carol Jantzen

Research paper thumbnail of Thermodynamic approach to prediction of the stability of proposed radwaste glasses

Assessment of the geologic performance of radwaste glasses requires extrapolation of finite tests... more Assessment of the geologic performance of radwaste glasses requires extrapolation of finite tests to very long times. A thermodynamic approach developed by Paul has been applied to leaching of both natural and synthetic glasses. This approach suggests that Savannah River waste glass should be as stable toward aqueous atttack as natural basalt. 11 references, 1 figure, 2 tables.

Research paper thumbnail of Relationship between borosilicate glass composition, structure, and durability test response (SRS)

The chemical durability of 30 glasses from the Na[sub 2]O [center dot] B[sub 2]O[sub 3] [center d... more The chemical durability of 30 glasses from the Na[sub 2]O [center dot] B[sub 2]O[sub 3] [center dot] SiO[sub 2] [center dot] Al[sub 2]O[sub 3] [center dot] Fe[sub 2]O[sub 3][center dot]CaO system was examined. Two standard leach tests, MCC-1P and PCT, were performed in unbuffered, deionized water. PCT tests were performed for durations up to twenty-four weeks to obtain glass dissolution rate data. Short-term MCC-1P test leachate solutions are determined by the glass composition. Long-term glass dissolution rates, however, are dependent on glass structure in addition to glass composition. The applicability of the free energy of hydration and other dissolution and durability models to this system is discussed.

Research paper thumbnail of Evaluation of THOR™Mineralized Waste Forms (Granular and Monolith) for the DOE Advanced Remediation Technologies (ART) Phase 2 Project

ACS Symposium Series, 2010

Research paper thumbnail of M-Area Mixed Waste Glasses: II. Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses

Research paper thumbnail of The determination of the Fe sup 2+ /Fe sup 3+ ratio in simulated nuclear waste glass by ion chromatography

Research paper thumbnail of How to recycle asbestos containing materials (ACM)

The current disposal of asbestos containing materials (ACM) in the private sector consists of sea... more The current disposal of asbestos containing materials (ACM) in the private sector consists of sealing asbestos wetted with water in plastic for safe transportation and burial in regulated land fills. This disposal methodology requires large disposal volumes especially for asbestos covered pipe and asbestos/fiberglass adhering to metal framework, e.g. filters. This wrap and bury technology precludes recycle of the asbestos, the pipe and/or the metal frameworks. Safe disposal of ACM at U.S. Department of Energy (DOE) sites, likewise, requires large disposal volumes in landfills for non-radioactive ACM and large disposal volumes in radioactive burial grounds for radioactive and suspect contaminated ACM. The availability of regulated disposal sites is rapidly diminishing causing recycle to be a more attractive option. Asbestos adhering to metal (e.g., pipes) can be recycled by safely removing the asbestos from the metal in a patented hot caustic bath which prevents airborne contamination /inhalation of asbestos fibers. The dissolution residue (caustic and asbestos) can be wet slurry fed to a melter and vitrified into a glass or glass-ceramic. Palex glasses, which are commercially manufactured, are shown to be preferred over conventional borosilicate glasses. The Palex glasses are alkali magnesium silicate glasses derived by substituting MgO for B{sub 2}O{submore » 3} in borosilicate type glasses. Palex glasses are very tolerant of the high MgO and high CaO content of the fillers used in forming asbestos coverings for pipes and found in boiler lashing, e.g., hydromagnesite (3MgCO{sub 3} Mg(OH){sub 2} 3H{sub 2}O) and plaster of paris, gypsum (CaSO{sub 4}). The high temperate of the vitrification process destroys the asbestos fibers and renders the asbestos non-hazardous, e.g., a glass or glass-ceramic. In this manner the glass or glass-ceramic produced can be recycled, e.g., glassphalt or glasscrete, as can the clean metal pipe or metal framework.« less

Research paper thumbnail of The relationship between glass viscosity and composition: A first principles model for vitrification of nuclear waste

This reportwas preparedas an accountof worksponsoredby ali agencyof the UnitedStates Government.N... more This reportwas preparedas an accountof worksponsoredby ali agencyof the UnitedStates Government.Neitherthe United StatesGovernment norany agencythereof,norany of their employees,make_any warranty, expressor implied, or assumesany legal liabilityor responsibilityfor the accuracy, completeness, or usefulnessof any information, apparatus,product, or processdisclosed, or representsthat its use wouldnot infringeprivatelyownedrights.Refer-0nc¢ hereinto any specificcommercialproduct, process, or serviceby tradename,trademark, manufacturer, or otherwisedees not necessarilyconstituteor imply its endorsement, recommendation, or favoringby the United States Government or any agency thereof.The views and opinionsof authors expressedherein do net ne.ccssarily state or reflect those of the UnitedStatesGovernment or any agencythereof.

Research paper thumbnail of Prediction of glass durability as a function of glass composition and test conditions: Thermodynamics and kinetics

The long-term durability of nuclear waste glasses can be predicted by comparing their performance... more The long-term durability of nuclear waste glasses can be predicted by comparing their performance to natural and ancient glasses. Glass durability is a function of the kinetic and thermodynamic stability of glass in solution. The relationship between the kinetic and thermodynamic aspects of glass durability can be understood when the relative contributions of glass composition and imposed test conditions are delineated. Glass durability has been shown to be a function of the thermodynamic hydration free energy which can be calculated from the glass composition. Hydration thermodynamics also furnishes a quantitative frame of reference to understand how various test parameters affect glass durability. Linear relationships have been determined between the logarithmic extent of hydration and the calculated hydration free energy for several different test geometries. Different test conditions result in different kinetic reactivity parameters such as the exposed glass surface area (SA), the leachant solution volume (V), and the length of time that the glass is in the leachant (t). Leachate concentrations are known to be a function of the kinetic test parameter (SAV)t. The relative durabilities of glasses, including pure silica, obsidians, nuclear waste glasses, medieval window glasses, and frit glasses define a plane in three dimensional ..delta..G/sub hyd/-concentration-(SAV)t space. At constant kinetic conditions, e.g., test geometry and test duration, the three dimensional plane is intersected at constant (SAV)t and the ..delta..G/sub hyd/-concentration plots have similar slopes. The slope represents the natural logarithm of the theoretical slope, (12.303 RT), for the rate of glass dissolution. 53 refs., 4 figs.

Research paper thumbnail of Treatability studies of actual listed waste sludges from the Oak Ridge Reservation (ORR)

Research paper thumbnail of Characterization of melter slurries vitrified by microwave

Research paper thumbnail of Durability of glasses from Pacific Northwest Laboratory Composition Variability Study-II (CVS-II)

Waste form producers at the Savannah River Site (SRS), West Valley Nuclear Fuel Services (WVNFS),... more Waste form producers at the Savannah River Site (SRS), West Valley Nuclear Fuel Services (WVNFS), and Hanford Waste Vitrification Project (HWVP) will immobilize high-level radioactive liquid waste in borosilicate g!ass. The glass will be poured into stainless steel canisters for eventual disposal in a geologic repository. The Department of Energy has defined a set of requirements for the canistered waste form which must be met in order to assure compatibility with, and acceptance by, the repository. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). 1 The cre'rent Waste Acceptance Preliminary Specification (WAPS) 1.3 requires the waste form producers to demonstrate control of the consistency of the final waste fom_ using the Product Consistency Test.2"3 The PCT is a crushed glass durability test which is (1) sensitive to glass composition and homogeneity, and (2) may have the potential to be rclat_'.xl to repository site

Research paper thumbnail of Solid state reactions in the system Al2O3Nd2O3CaO: A system pertinent to radioactive waste disposal

Materials Research Bulletin, 1981

High alumina ceramic phases are promising crystalline hosts for containment of radioactive wastes... more High alumina ceramic phases are promising crystalline hosts for containment of radioactive wastes. The distribution of lanthanons in the calcia-alumina rich compositions, e.g., in CaAll2Olg-LnAIi1018 type solid solutions, has been explored by using Nd as a model 4f element. The remaining phase compatibilities and solid solution ranges have been examined at 1300°C.

Research paper thumbnail of Approved by: W.L. Tamosaitis, Research Manager

This document was prepared in conjunction with work accomplished under Contract No. DE-

Research paper thumbnail of Vitrification of F006 plating waste sludge by Reactive Additive Stabilization Process (RASP)

Solidification into glass of nickel-on-uranium plating wastewater treatment plant sludge (F006 Mi... more Solidification into glass of nickel-on-uranium plating wastewater treatment plant sludge (F006 Mixed Waste) has been demonstrated at the Savannah River She (SRS). Vitrification using high surface area additives, the Reactive Additive Stabilization Process (RASP), greatly enhanced the solubility and retention of heavy metals In glass. The bench-scale tests using RASP achieved 76 wt% waste loading In both soda-lime-silica and borosilicate

Research paper thumbnail of Hydroceramic Binders

Calcine was made from the Hanford SBW simulant by mixing it with sucrose and metakaolin in a weig... more Calcine was made from the Hanford SBW simulant by mixing it with sucrose and metakaolin in a weight ratio of 50 SBW: 4.2 sucrose: 63.7 metakaolin, drying the “mud-like” paste at 90 C for overnight and then firing it in air at 525 C for 10 hours.

Research paper thumbnail of Fluidized Bed Steam Reforming Mineralization for High Organic and Nitrate Waste Streams for the Global Nuclear Energy …

Description/Abstract Waste streams that may be generated by the Global Nuclear Energy Partnership... more Description/Abstract Waste streams that may be generated by the Global Nuclear Energy Partnership (GNEP) Advanced Energy Initiative may contain significant quantities of organics (0-53 wt%) and/or nitrates (0-56 wt%). Decomposition of high nitrate streams ...

Research paper thumbnail of On spinodal decomposition in Fe-free pyroxenes

... Tweed structures in rapidly cooled pyrox-enes have been attributed to decompositon by a spino... more ... Tweed structures in rapidly cooled pyrox-enes have been attributed to decompositon by a spinodal mechanism while slower cooling rates (<10 ... operative spinodal mechanism in Fe-free pyroxenes, as in, eg, a recent review of pyroxene crystal chemistry by Cameron and Papike ...

Research paper thumbnail of Method for treating materials for solidification

A method for treating materials such as wastes for solidification to form a solid, substantially ... more A method for treating materials such as wastes for solidification to form a solid, substantially nonleachable product. Addition of reactive silica rather than ordinary silica to the material when bringing the initial molar ratio of its silica constituent to a desired ratio within a preselected range increases the solubility and retention of the materials in the solidified matrix. Materials include hazardous, radioactive, mixed, and heavy metal species. Amounts of other constituents of the material, in addition to its silica content are also added so that the molar ratio of each of these constituents is within the preselected ranges for the final solidified product. The mixture is then solidified by cement solidification or vitrification. The method can be used to treat a variety of wastes, including but not limited to spent filter aids from waste water treatment, waste sludges, combinations of spent filter aids and waste sludges, combinations of supernate and waste sludges, incinera...

Research paper thumbnail of Scaled impulse loading for liquid hydraulic response in IFE thick-liquid chamber experiments

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2001

Research paper thumbnail of Radioactive Waste-Portland Cement Systems: II, Leaching Characteristics

Journal of the American Ceramic Society, 1984

Crystal chemical stabilization of radioactive wastes can be achieved during clinkering of ordinar... more Crystal chemical stabilization of radioactive wastes can be achieved during clinkering of ordinary portland cement. Crys-tallographic relations predict that the radionuclide partitioning in the anhydrous clinkered phases will be maintained in the hydration products. The resulting hydration products are considered to be cementitious hydroxylated radiophases. Simulated leaching experiments demonstrate that the hydroxylated phases are stable and that waste element release rates are lower than for other cementitious waste forms. The formation of tobermorite as a reaction product limits the release of cesium. Radionuclide fixation is described in the context of commercial waste-cement systems, but is applicable to transuranic, medium- and low-level wastes.

Research paper thumbnail of Thermodynamic approach to prediction of the stability of proposed radwaste glasses

Assessment of the geologic performance of radwaste glasses requires extrapolation of finite tests... more Assessment of the geologic performance of radwaste glasses requires extrapolation of finite tests to very long times. A thermodynamic approach developed by Paul has been applied to leaching of both natural and synthetic glasses. This approach suggests that Savannah River waste glass should be as stable toward aqueous atttack as natural basalt. 11 references, 1 figure, 2 tables.

Research paper thumbnail of Relationship between borosilicate glass composition, structure, and durability test response (SRS)

The chemical durability of 30 glasses from the Na[sub 2]O [center dot] B[sub 2]O[sub 3] [center d... more The chemical durability of 30 glasses from the Na[sub 2]O [center dot] B[sub 2]O[sub 3] [center dot] SiO[sub 2] [center dot] Al[sub 2]O[sub 3] [center dot] Fe[sub 2]O[sub 3][center dot]CaO system was examined. Two standard leach tests, MCC-1P and PCT, were performed in unbuffered, deionized water. PCT tests were performed for durations up to twenty-four weeks to obtain glass dissolution rate data. Short-term MCC-1P test leachate solutions are determined by the glass composition. Long-term glass dissolution rates, however, are dependent on glass structure in addition to glass composition. The applicability of the free energy of hydration and other dissolution and durability models to this system is discussed.

Research paper thumbnail of Evaluation of THOR™Mineralized Waste Forms (Granular and Monolith) for the DOE Advanced Remediation Technologies (ART) Phase 2 Project

ACS Symposium Series, 2010

Research paper thumbnail of M-Area Mixed Waste Glasses: II. Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses

Research paper thumbnail of The determination of the Fe sup 2+ /Fe sup 3+ ratio in simulated nuclear waste glass by ion chromatography

Research paper thumbnail of How to recycle asbestos containing materials (ACM)

The current disposal of asbestos containing materials (ACM) in the private sector consists of sea... more The current disposal of asbestos containing materials (ACM) in the private sector consists of sealing asbestos wetted with water in plastic for safe transportation and burial in regulated land fills. This disposal methodology requires large disposal volumes especially for asbestos covered pipe and asbestos/fiberglass adhering to metal framework, e.g. filters. This wrap and bury technology precludes recycle of the asbestos, the pipe and/or the metal frameworks. Safe disposal of ACM at U.S. Department of Energy (DOE) sites, likewise, requires large disposal volumes in landfills for non-radioactive ACM and large disposal volumes in radioactive burial grounds for radioactive and suspect contaminated ACM. The availability of regulated disposal sites is rapidly diminishing causing recycle to be a more attractive option. Asbestos adhering to metal (e.g., pipes) can be recycled by safely removing the asbestos from the metal in a patented hot caustic bath which prevents airborne contamination /inhalation of asbestos fibers. The dissolution residue (caustic and asbestos) can be wet slurry fed to a melter and vitrified into a glass or glass-ceramic. Palex glasses, which are commercially manufactured, are shown to be preferred over conventional borosilicate glasses. The Palex glasses are alkali magnesium silicate glasses derived by substituting MgO for B{sub 2}O{submore » 3} in borosilicate type glasses. Palex glasses are very tolerant of the high MgO and high CaO content of the fillers used in forming asbestos coverings for pipes and found in boiler lashing, e.g., hydromagnesite (3MgCO{sub 3} Mg(OH){sub 2} 3H{sub 2}O) and plaster of paris, gypsum (CaSO{sub 4}). The high temperate of the vitrification process destroys the asbestos fibers and renders the asbestos non-hazardous, e.g., a glass or glass-ceramic. In this manner the glass or glass-ceramic produced can be recycled, e.g., glassphalt or glasscrete, as can the clean metal pipe or metal framework.« less

Research paper thumbnail of The relationship between glass viscosity and composition: A first principles model for vitrification of nuclear waste

This reportwas preparedas an accountof worksponsoredby ali agencyof the UnitedStates Government.N... more This reportwas preparedas an accountof worksponsoredby ali agencyof the UnitedStates Government.Neitherthe United StatesGovernment norany agencythereof,norany of their employees,make_any warranty, expressor implied, or assumesany legal liabilityor responsibilityfor the accuracy, completeness, or usefulnessof any information, apparatus,product, or processdisclosed, or representsthat its use wouldnot infringeprivatelyownedrights.Refer-0nc¢ hereinto any specificcommercialproduct, process, or serviceby tradename,trademark, manufacturer, or otherwisedees not necessarilyconstituteor imply its endorsement, recommendation, or favoringby the United States Government or any agency thereof.The views and opinionsof authors expressedherein do net ne.ccssarily state or reflect those of the UnitedStatesGovernment or any agencythereof.

Research paper thumbnail of Prediction of glass durability as a function of glass composition and test conditions: Thermodynamics and kinetics

The long-term durability of nuclear waste glasses can be predicted by comparing their performance... more The long-term durability of nuclear waste glasses can be predicted by comparing their performance to natural and ancient glasses. Glass durability is a function of the kinetic and thermodynamic stability of glass in solution. The relationship between the kinetic and thermodynamic aspects of glass durability can be understood when the relative contributions of glass composition and imposed test conditions are delineated. Glass durability has been shown to be a function of the thermodynamic hydration free energy which can be calculated from the glass composition. Hydration thermodynamics also furnishes a quantitative frame of reference to understand how various test parameters affect glass durability. Linear relationships have been determined between the logarithmic extent of hydration and the calculated hydration free energy for several different test geometries. Different test conditions result in different kinetic reactivity parameters such as the exposed glass surface area (SA), the leachant solution volume (V), and the length of time that the glass is in the leachant (t). Leachate concentrations are known to be a function of the kinetic test parameter (SAV)t. The relative durabilities of glasses, including pure silica, obsidians, nuclear waste glasses, medieval window glasses, and frit glasses define a plane in three dimensional ..delta..G/sub hyd/-concentration-(SAV)t space. At constant kinetic conditions, e.g., test geometry and test duration, the three dimensional plane is intersected at constant (SAV)t and the ..delta..G/sub hyd/-concentration plots have similar slopes. The slope represents the natural logarithm of the theoretical slope, (12.303 RT), for the rate of glass dissolution. 53 refs., 4 figs.

Research paper thumbnail of Treatability studies of actual listed waste sludges from the Oak Ridge Reservation (ORR)

Research paper thumbnail of Characterization of melter slurries vitrified by microwave

Research paper thumbnail of Durability of glasses from Pacific Northwest Laboratory Composition Variability Study-II (CVS-II)

Waste form producers at the Savannah River Site (SRS), West Valley Nuclear Fuel Services (WVNFS),... more Waste form producers at the Savannah River Site (SRS), West Valley Nuclear Fuel Services (WVNFS), and Hanford Waste Vitrification Project (HWVP) will immobilize high-level radioactive liquid waste in borosilicate g!ass. The glass will be poured into stainless steel canisters for eventual disposal in a geologic repository. The Department of Energy has defined a set of requirements for the canistered waste form which must be met in order to assure compatibility with, and acceptance by, the repository. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). 1 The cre'rent Waste Acceptance Preliminary Specification (WAPS) 1.3 requires the waste form producers to demonstrate control of the consistency of the final waste fom_ using the Product Consistency Test.2"3 The PCT is a crushed glass durability test which is (1) sensitive to glass composition and homogeneity, and (2) may have the potential to be rclat_'.xl to repository site

Research paper thumbnail of Solid state reactions in the system Al2O3Nd2O3CaO: A system pertinent to radioactive waste disposal

Materials Research Bulletin, 1981

High alumina ceramic phases are promising crystalline hosts for containment of radioactive wastes... more High alumina ceramic phases are promising crystalline hosts for containment of radioactive wastes. The distribution of lanthanons in the calcia-alumina rich compositions, e.g., in CaAll2Olg-LnAIi1018 type solid solutions, has been explored by using Nd as a model 4f element. The remaining phase compatibilities and solid solution ranges have been examined at 1300°C.

Research paper thumbnail of Approved by: W.L. Tamosaitis, Research Manager

This document was prepared in conjunction with work accomplished under Contract No. DE-

Research paper thumbnail of Vitrification of F006 plating waste sludge by Reactive Additive Stabilization Process (RASP)

Solidification into glass of nickel-on-uranium plating wastewater treatment plant sludge (F006 Mi... more Solidification into glass of nickel-on-uranium plating wastewater treatment plant sludge (F006 Mixed Waste) has been demonstrated at the Savannah River She (SRS). Vitrification using high surface area additives, the Reactive Additive Stabilization Process (RASP), greatly enhanced the solubility and retention of heavy metals In glass. The bench-scale tests using RASP achieved 76 wt% waste loading In both soda-lime-silica and borosilicate

Research paper thumbnail of Hydroceramic Binders

Calcine was made from the Hanford SBW simulant by mixing it with sucrose and metakaolin in a weig... more Calcine was made from the Hanford SBW simulant by mixing it with sucrose and metakaolin in a weight ratio of 50 SBW: 4.2 sucrose: 63.7 metakaolin, drying the “mud-like” paste at 90 C for overnight and then firing it in air at 525 C for 10 hours.

Research paper thumbnail of Fluidized Bed Steam Reforming Mineralization for High Organic and Nitrate Waste Streams for the Global Nuclear Energy …

Description/Abstract Waste streams that may be generated by the Global Nuclear Energy Partnership... more Description/Abstract Waste streams that may be generated by the Global Nuclear Energy Partnership (GNEP) Advanced Energy Initiative may contain significant quantities of organics (0-53 wt%) and/or nitrates (0-56 wt%). Decomposition of high nitrate streams ...

Research paper thumbnail of On spinodal decomposition in Fe-free pyroxenes

... Tweed structures in rapidly cooled pyrox-enes have been attributed to decompositon by a spino... more ... Tweed structures in rapidly cooled pyrox-enes have been attributed to decompositon by a spinodal mechanism while slower cooling rates (<10 ... operative spinodal mechanism in Fe-free pyroxenes, as in, eg, a recent review of pyroxene crystal chemistry by Cameron and Papike ...

Research paper thumbnail of Method for treating materials for solidification

A method for treating materials such as wastes for solidification to form a solid, substantially ... more A method for treating materials such as wastes for solidification to form a solid, substantially nonleachable product. Addition of reactive silica rather than ordinary silica to the material when bringing the initial molar ratio of its silica constituent to a desired ratio within a preselected range increases the solubility and retention of the materials in the solidified matrix. Materials include hazardous, radioactive, mixed, and heavy metal species. Amounts of other constituents of the material, in addition to its silica content are also added so that the molar ratio of each of these constituents is within the preselected ranges for the final solidified product. The mixture is then solidified by cement solidification or vitrification. The method can be used to treat a variety of wastes, including but not limited to spent filter aids from waste water treatment, waste sludges, combinations of spent filter aids and waste sludges, combinations of supernate and waste sludges, incinera...

Research paper thumbnail of Scaled impulse loading for liquid hydraulic response in IFE thick-liquid chamber experiments

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2001

Research paper thumbnail of Radioactive Waste-Portland Cement Systems: II, Leaching Characteristics

Journal of the American Ceramic Society, 1984

Crystal chemical stabilization of radioactive wastes can be achieved during clinkering of ordinar... more Crystal chemical stabilization of radioactive wastes can be achieved during clinkering of ordinary portland cement. Crys-tallographic relations predict that the radionuclide partitioning in the anhydrous clinkered phases will be maintained in the hydration products. The resulting hydration products are considered to be cementitious hydroxylated radiophases. Simulated leaching experiments demonstrate that the hydroxylated phases are stable and that waste element release rates are lower than for other cementitious waste forms. The formation of tobermorite as a reaction product limits the release of cesium. Radionuclide fixation is described in the context of commercial waste-cement systems, but is applicable to transuranic, medium- and low-level wastes.