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Papers by Guillermo del Cul

Research paper thumbnail of Hydrochlorination at 200°C Relevant to the Removal of Cladding from Spent Nuclear Fuel

U.S. Department of Energy Office of Scientific and Technical Information - OSTI OAI, Jun 1, 2021

Research paper thumbnail of Fission Product Measurement and Off-Gas Scrubbing for Molten Salt Reactors

Transactions of the American Nuclear Society - Volume 121, 2019

Research paper thumbnail of Visible and Near-IR Spectroscopic Studies of UCl4 in a Basic Ambient Temperature Melt: The Observation of a Possible Geometric Distorted UCl62− Species and the Evidence for the Hydrogen-Bond in the Melt

ECS Proceedings Volumes, 1994

Research paper thumbnail of ChemInform Abstract: Solubilities of Uranium(IV) Dioxide in Magnesium Chloride, Calcium Chloride, and Aluminum Chloride Melts: A Comparative Study

Research paper thumbnail of Liquid Hydrofluoric Acid Sorption Using Solid Media - Part 1

Research paper thumbnail of Water Content of Organic Solvents and their Relationship to Extraction of Nitric and Acetic Acid from UREX+ Streams

Separation Science and Technology, 2013

Research paper thumbnail of Water and Mean Ionic Activities of Aqueous HNO 3 Solutions Calculated from an Extension of the Brunauer-Emmett-Teller (BET) Model

Separation Science and Technology, 2010

The objective for this research was to employ the extended adsorption isotherm (EAI) to develop a... more The objective for this research was to employ the extended adsorption isotherm (EAI) to develop a predictive relationship between the activity of H2O (aw) and the mean ionic activity (a±) of aqueous HNO3. The EAI model is a calculative approach to the estimation of solutions for activities of highly non-ideal chemical systems and is the collective efforts of Stokes and

Research paper thumbnail of Extracting Acetic Acid from Acidic Solutions

Separation Science and Technology, 2008

Abstract In the UREX+ process, acetic acid must be removed from the raffinate stream to avoid int... more Abstract In the UREX+ process, acetic acid must be removed from the raffinate stream to avoid interference with the recovery and recycle of nitric acid solutions. Solvent extraction was selected to be the most promising approach to accomplish this cleanup. Acetic acid ...

Research paper thumbnail of Thermodynamics of Acetic Acid (aq) Calculated from the Modified Adsorption Isotherm Model for Aqueous Electrolytes

Separation Science and Technology, 2008

The modified adsorption isotherm model, incorporating the Stokes-Robinson modification of the Bru... more The modified adsorption isotherm model, incorporating the Stokes-Robinson modification of the Brunauer-Emmett-Teller (BET) adsorption isotherm, is used to calculate the activity of the organic acid and water, and the liquidus curve. This is the first known use of the modified adsorption isotherm for estimation of thermodynamic information for aqueous organic acid solutions and one of few works using the model

Research paper thumbnail of Some investigations of the reaction of activated charcoal with fluorine and uranium hexafluoride

Journal of Fluorine Chemistry, 2000

Research paper thumbnail of Polarized Raman spectra of single-crystal lanthanide oxychlorides

Journal of Alloys and Compounds, 1993

Research paper thumbnail of Molten fluoride fuel salt chemistry

AIP Conference Proceedings, 1995

Research paper thumbnail of Development of Advanced Cermet Waste Forms

The growing interest in the expansion of nuclear energy in the United States is widely acknowledg... more The growing interest in the expansion of nuclear energy in the United States is widely acknowledged. While public support for the expanded use of nuclear power is relatively high, the disposition of the resulting waste remains a significant concern. A Blue Ribbon Commission on America’s Nuclear Future has recently been established at the direction of the President to examine options for the permanent disposal of high-level nuclear waste. Waste forms other than glass for high-level-waste (HLW) disposal are expected to be included in this assessment. The Oak Ridge National Laboratory has been conducting research to develop a cermet waste form for the immobilization of the HLW generated in processing of used nuclear fuel. The cermet waste form will allow emplacement of the high-radioactivity, high decay heat–generating fission products, Cs/Ba and Sr/Y, along with other oxide-forming fission products in a ceramic or oxide form, distributed within a high-thermal-conductivity metallic mat...

Research paper thumbnail of Demonstration of Integrated PostIrradiation Process Steps forMultikilogram Amounts of Low- and High-Burnup Used Nuclear Fuels

Research paper thumbnail of Technology Advancement for Recycle of Zirconium From Used Nuclear Fuel Cladding

Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (U... more Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (UNF) cladding can be recovered in sufficient purity to permit re-use, and if the recovery process can be operated economically. Initial tests are being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery process and determine the degree of purification that can be obtained. Early results indicate that quantitative recovery can be accomplished and product contamination with alloy constituents can be controlled sufficiently to meet purification requirements. Future tests with actual radioactive UNF cladding are planned.

Research paper thumbnail of Processing of spent TRISO-coated reactor fuels : Milling of fuel to support a grind-leach process

Research paper thumbnail of Advanced head-end processing of spent fuel : A hybrid front-end

Transactions of the American Nuclear Society, 2005

Research paper thumbnail of Processing of spent TRISO-coated gen IV reactor fuels : Mechanical head-end processing

Transactions of the American Nuclear Society, 2005

ABSTRACT The crush-leach process was investigated as a method to treat GEN IV TRISO-coated reacto... more ABSTRACT The crush-leach process was investigated as a method to treat GEN IV TRISO-coated reactor fuels. The method retains the bulk of the carbon components in elemental form, which is favorable for achieving waste reduction goals. A literature review identified the potential problems with this technique. Leaching of simulated crushed TRISO-coated fuel and extraction behavior of the separated leaching solution were tested at the laboratory scale. Very finely divided carbon used in the preparation of simulants was difficult to separate by filtering, indicating the need to carefully control particle size and/or use alternative solid-liquid separation methods. In the solvent extraction tests, the production of foams or emulsions was not observed. Measured distribution ratios for uranium were slightly larger than predicted by accepted models. This increase may be due to small concentrations of organics, but the experimental results are not conclusive. Although the data do not strongly indicate effects by a contaminating organic agent, the organic species may exist in small concentrations.

Research paper thumbnail of Removal of Acetic Acid from a UREX + Raffinate Stream

In the UREX+ process, acetohydroxamic acid is added to the UREX step to suppress plutonium extrac... more In the UREX+ process, acetohydroxamic acid is added to the UREX step to suppress plutonium extraction. Hydrolysis of acetohydroxamic acid (AHA) produces acetic acid and hydroxyl ammonium nitrate (HAN). The capability to remove acetic acid from aqueous process solutions is desirable as UREX+ flowsheets continue to evolve. Reasons for acetic acid removal include enabling recycle of the nitric acid solution and prevention of problems in downstream process steps. After a literature review, solvent extraction was determined to be the most promising approach for removal of acetic acid at the low concentrations involved. The goal was to identify a solvent that is both insoluble in the aqueous phase and will selectively remove acetic acid. Solutions of tributylphosphate (TBP) have been shown to selectively extract acetic acid over nitric acid with sufficiently high distribution coefficients. Extractant solutions tested in this study include TBP in dodecane and TBP in phenyltrifluoromethyl s...

Research paper thumbnail of Fission Product Separation/Extraction Techniques

Research paper thumbnail of Hydrochlorination at 200°C Relevant to the Removal of Cladding from Spent Nuclear Fuel

U.S. Department of Energy Office of Scientific and Technical Information - OSTI OAI, Jun 1, 2021

Research paper thumbnail of Fission Product Measurement and Off-Gas Scrubbing for Molten Salt Reactors

Transactions of the American Nuclear Society - Volume 121, 2019

Research paper thumbnail of Visible and Near-IR Spectroscopic Studies of UCl4 in a Basic Ambient Temperature Melt: The Observation of a Possible Geometric Distorted UCl62− Species and the Evidence for the Hydrogen-Bond in the Melt

ECS Proceedings Volumes, 1994

Research paper thumbnail of ChemInform Abstract: Solubilities of Uranium(IV) Dioxide in Magnesium Chloride, Calcium Chloride, and Aluminum Chloride Melts: A Comparative Study

Research paper thumbnail of Liquid Hydrofluoric Acid Sorption Using Solid Media - Part 1

Research paper thumbnail of Water Content of Organic Solvents and their Relationship to Extraction of Nitric and Acetic Acid from UREX+ Streams

Separation Science and Technology, 2013

Research paper thumbnail of Water and Mean Ionic Activities of Aqueous HNO 3 Solutions Calculated from an Extension of the Brunauer-Emmett-Teller (BET) Model

Separation Science and Technology, 2010

The objective for this research was to employ the extended adsorption isotherm (EAI) to develop a... more The objective for this research was to employ the extended adsorption isotherm (EAI) to develop a predictive relationship between the activity of H2O (aw) and the mean ionic activity (a±) of aqueous HNO3. The EAI model is a calculative approach to the estimation of solutions for activities of highly non-ideal chemical systems and is the collective efforts of Stokes and

Research paper thumbnail of Extracting Acetic Acid from Acidic Solutions

Separation Science and Technology, 2008

Abstract In the UREX+ process, acetic acid must be removed from the raffinate stream to avoid int... more Abstract In the UREX+ process, acetic acid must be removed from the raffinate stream to avoid interference with the recovery and recycle of nitric acid solutions. Solvent extraction was selected to be the most promising approach to accomplish this cleanup. Acetic acid ...

Research paper thumbnail of Thermodynamics of Acetic Acid (aq) Calculated from the Modified Adsorption Isotherm Model for Aqueous Electrolytes

Separation Science and Technology, 2008

The modified adsorption isotherm model, incorporating the Stokes-Robinson modification of the Bru... more The modified adsorption isotherm model, incorporating the Stokes-Robinson modification of the Brunauer-Emmett-Teller (BET) adsorption isotherm, is used to calculate the activity of the organic acid and water, and the liquidus curve. This is the first known use of the modified adsorption isotherm for estimation of thermodynamic information for aqueous organic acid solutions and one of few works using the model

Research paper thumbnail of Some investigations of the reaction of activated charcoal with fluorine and uranium hexafluoride

Journal of Fluorine Chemistry, 2000

Research paper thumbnail of Polarized Raman spectra of single-crystal lanthanide oxychlorides

Journal of Alloys and Compounds, 1993

Research paper thumbnail of Molten fluoride fuel salt chemistry

AIP Conference Proceedings, 1995

Research paper thumbnail of Development of Advanced Cermet Waste Forms

The growing interest in the expansion of nuclear energy in the United States is widely acknowledg... more The growing interest in the expansion of nuclear energy in the United States is widely acknowledged. While public support for the expanded use of nuclear power is relatively high, the disposition of the resulting waste remains a significant concern. A Blue Ribbon Commission on America’s Nuclear Future has recently been established at the direction of the President to examine options for the permanent disposal of high-level nuclear waste. Waste forms other than glass for high-level-waste (HLW) disposal are expected to be included in this assessment. The Oak Ridge National Laboratory has been conducting research to develop a cermet waste form for the immobilization of the HLW generated in processing of used nuclear fuel. The cermet waste form will allow emplacement of the high-radioactivity, high decay heat–generating fission products, Cs/Ba and Sr/Y, along with other oxide-forming fission products in a ceramic or oxide form, distributed within a high-thermal-conductivity metallic mat...

Research paper thumbnail of Demonstration of Integrated PostIrradiation Process Steps forMultikilogram Amounts of Low- and High-Burnup Used Nuclear Fuels

Research paper thumbnail of Technology Advancement for Recycle of Zirconium From Used Nuclear Fuel Cladding

Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (U... more Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (UNF) cladding can be recovered in sufficient purity to permit re-use, and if the recovery process can be operated economically. Initial tests are being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery process and determine the degree of purification that can be obtained. Early results indicate that quantitative recovery can be accomplished and product contamination with alloy constituents can be controlled sufficiently to meet purification requirements. Future tests with actual radioactive UNF cladding are planned.

Research paper thumbnail of Processing of spent TRISO-coated reactor fuels : Milling of fuel to support a grind-leach process

Research paper thumbnail of Advanced head-end processing of spent fuel : A hybrid front-end

Transactions of the American Nuclear Society, 2005

Research paper thumbnail of Processing of spent TRISO-coated gen IV reactor fuels : Mechanical head-end processing

Transactions of the American Nuclear Society, 2005

ABSTRACT The crush-leach process was investigated as a method to treat GEN IV TRISO-coated reacto... more ABSTRACT The crush-leach process was investigated as a method to treat GEN IV TRISO-coated reactor fuels. The method retains the bulk of the carbon components in elemental form, which is favorable for achieving waste reduction goals. A literature review identified the potential problems with this technique. Leaching of simulated crushed TRISO-coated fuel and extraction behavior of the separated leaching solution were tested at the laboratory scale. Very finely divided carbon used in the preparation of simulants was difficult to separate by filtering, indicating the need to carefully control particle size and/or use alternative solid-liquid separation methods. In the solvent extraction tests, the production of foams or emulsions was not observed. Measured distribution ratios for uranium were slightly larger than predicted by accepted models. This increase may be due to small concentrations of organics, but the experimental results are not conclusive. Although the data do not strongly indicate effects by a contaminating organic agent, the organic species may exist in small concentrations.

Research paper thumbnail of Removal of Acetic Acid from a UREX + Raffinate Stream

In the UREX+ process, acetohydroxamic acid is added to the UREX step to suppress plutonium extrac... more In the UREX+ process, acetohydroxamic acid is added to the UREX step to suppress plutonium extraction. Hydrolysis of acetohydroxamic acid (AHA) produces acetic acid and hydroxyl ammonium nitrate (HAN). The capability to remove acetic acid from aqueous process solutions is desirable as UREX+ flowsheets continue to evolve. Reasons for acetic acid removal include enabling recycle of the nitric acid solution and prevention of problems in downstream process steps. After a literature review, solvent extraction was determined to be the most promising approach for removal of acetic acid at the low concentrations involved. The goal was to identify a solvent that is both insoluble in the aqueous phase and will selectively remove acetic acid. Solutions of tributylphosphate (TBP) have been shown to selectively extract acetic acid over nitric acid with sufficiently high distribution coefficients. Extractant solutions tested in this study include TBP in dodecane and TBP in phenyltrifluoromethyl s...

Research paper thumbnail of Fission Product Separation/Extraction Techniques