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Extraction of lanthanides from acidic solution using tributyl phosphate modified supercritical carbon dioxide

Analytical chemistry (Washington), 1994-07, Vol.66 (13), p.2190-2193

1994

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Chemical basis for pyrochemical reprocessing of nuclear fuel

Industrial & engineering chemistry research, 1991-01, Vol.30 (1), p.141-145

Ackerman, John P

1991

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Salt-Occluded Zeolites as an Immobilization Matrix for Chloride Waste Salt

Journal of the American Ceramic Society, 1993-11, Vol.76 (11), p.2826-2832

1993

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EXTRACTION OF U(VI), Pu(IV) AND Th(IV) BY SOME TRIALKYL PHOSPHATES

Solvent extraction and ion exchange, 1994-08, Vol.12 (4), p.727-744

1994

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The Truex Process--a Process for the Extraction of the Transuranic Elements From Nitric Acid Wastes Utilizing Modified Purex Solvent

Solvent extraction and ion exchange, 1985-01, Vol.3 (1-2), p.75-109

1985

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Influence of Membrane Solvent on Strontium Transport from Reprocessing Concentrate Solutions through Flat-Sheet-Supported Liquid Membranes

Separation science and technology, 1993-08, Vol.28 (11-12), p.2007-2022

1993

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SEPARATION OF ACTINIDES AND LANTHANIDES FROM ACIDIC NUCLEAR WASTES BY SUPPORTED LIQUID MEMBRANES

Solvent extraction and ion exchange, 1985-02, Vol.3 (1-2), p.111-147

1985

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Partitioning of actinides and fission products in highly-active raffinate from purex process by mixer-settlers

Solvent extraction and ion exchange, 1992-12, Vol.10:5

1992

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Radioactive Wastes

Water environment research, 1994-06, Vol.66 (4), p.465-475

1994

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New Separation Process for Neptunium, Plutonium, and Uranium Using Butyraldehydes as Reductants in Reprocessing

Nuclear technology, 1993-06, Vol.102 (3), p.341-352

1993

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Mechanism of improved corrosion resistance of type 304L stainless steel, nitric acid grade, in nitric acid environments

Journal of materials engineering and performance, 1994-12, Vol.3 (6), p.699-705

1994

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THE EFFECT OF DILUENT ON THIRD PHASE FORMATION IN THORIUM NITRATE - TBP SYSTEM: SOME NOVEL EMPIRICAL CORRELATIONS

Solvent extraction and ion exchange, 1993-05, Vol.11 (4), p.645-662

1993

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An improved finite difference method for fixed-bed multicomponent sorption

AIChE journal, 1991-02, Vol.37 (2), p.244-254

1991

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Incorporation of Transuranic Elements in Titanate Nuclear Waste Ceramics

Journal of the American Ceramic Society, 1990-02, Vol.73 (2), p.370-378

1990

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Protecting groups in the preparation of thiolate complexes of technetium

Inorganic chemistry, 1990-08, Vol.29 (16), p.2948-2951

1990

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Reactivity Feedback Mechanisms in Aqueous Fissile Solutions

Nuclear science and engineering, 1993-09, Vol.115 (1), p.50-61

Kornreich, Drew E.

1993

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Polyphase Ceramic for Consolidating Nuclear Waste Compositions with High Zr-Cd-Na Content

Journal of the American Ceramic Society, 1990-07, Vol.73 (7), p.1901-1906

1990

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Radiation testing of optical fibers for a hot-cell photometer

IEEE transactions on nuclear science, 1993-06, Vol.40 (3), p.307-309

Chesser, J.B.

1993

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IEEE_Xplore

The Iodine Species and Their Behavior in the Dissolution of Spent-Fuel Specimens

Nuclear technology, 1992-07, Vol.99 (1), p.70-79

1992

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A SPREADSHEET ALGORITHM FOR STAGEWISE SOLVENT EXTRACTION

Solvent extraction and ion exchange, 1994-10, Vol.12 (5), p.909-930

1994

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SEPARATION AND RECOVERY OF PLUTONIUM FROM OXALATE SUPERNATANT USING CMPO

Solvent extraction and ion exchange, 1994-08, Vol.12 (4), p.745-763

1994

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Technetium electrochemistry. 7. Electrochemical and spectroelectrochemical studies on technetium(III) and -(II) complexes containing polypyridyl ligands

Inorganic chemistry, 1991-02, Vol.30 (4), p.688-693

1991

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Selected Alkyl(phenyl)-N,N-dialkylcarbamoylmethylphosphine Oxides as Extractants for Am(III) from Nitric Acid Media

Separation science and technology, 1982-07, Vol.17 (10), p.1261-1279

1982

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Criticality Data and Validation Studies of Mixed-Oxide Fuel Pin Arrays in Pu+U+Gd Nitrate

Nuclear technology, 1994-09, Vol.107 (3), p.340-355

1994

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Cadmium Transport through Molten Salts in the Reprocessing of Spent Fuel for the Integral Fast Reactor

Nuclear technology, 1993-06, Vol.102 (3), p.331-340

1993

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Extraction of lanthanides from acidic solution using tributyl phosphate modified supercritical carbon dioxide

Chemical basis for pyrochemical reprocessing of nuclear fuel

Salt-Occluded Zeolites as an Immobilization Matrix for Chloride Waste Salt

EXTRACTION OF U(VI), Pu(IV) AND Th(IV) BY SOME TRIALKYL PHOSPHATES

The Truex Process--a Process for the Extraction of the Transuranic Elements From Nitric Acid Wastes Utilizing Modified Purex Solvent

Influence of Membrane Solvent on Strontium Transport from Reprocessing Concentrate Solutions through Flat-Sheet-Supported Liquid Membranes

SEPARATION OF ACTINIDES AND LANTHANIDES FROM ACIDIC NUCLEAR WASTES BY SUPPORTED LIQUID MEMBRANES

Partitioning of actinides and fission products in highly-active raffinate from purex process by mixer-settlers

Radioactive Wastes

New Separation Process for Neptunium, Plutonium, and Uranium Using Butyraldehydes as Reductants in Reprocessing

Mechanism of improved corrosion resistance of type 304L stainless steel, nitric acid grade, in nitric acid environments

THE EFFECT OF DILUENT ON THIRD PHASE FORMATION IN THORIUM NITRATE - TBP SYSTEM: SOME NOVEL EMPIRICAL CORRELATIONS

An improved finite difference method for fixed-bed multicomponent sorption

Incorporation of Transuranic Elements in Titanate Nuclear Waste Ceramics

Protecting groups in the preparation of thiolate complexes of technetium

Reactivity Feedback Mechanisms in Aqueous Fissile Solutions

Polyphase Ceramic for Consolidating Nuclear Waste Compositions with High Zr-Cd-Na Content

Radiation testing of optical fibers for a hot-cell photometer

The Iodine Species and Their Behavior in the Dissolution of Spent-Fuel Specimens

A SPREADSHEET ALGORITHM FOR STAGEWISE SOLVENT EXTRACTION

SEPARATION AND RECOVERY OF PLUTONIUM FROM OXALATE SUPERNATANT USING CMPO

Technetium electrochemistry. 7. Electrochemical and spectroelectrochemical studies on technetium(III) and -(II) complexes containing polypyridyl ligands

Selected Alkyl(phenyl)-N,N-dialkylcarbamoylmethylphosphine Oxides as Extractants for Am(III) from Nitric Acid Media

Criticality Data and Validation Studies of Mixed-Oxide Fuel Pin Arrays in Pu+U+Gd Nitrate

Cadmium Transport through Molten Salts in the Reprocessing of Spent Fuel for the Integral Fast Reactor

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