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Conversion of radioactive and hazardous chemical wastes into borosilicate glass using the glass material oxidation and dissolution system

Waste management (Elmsford), 1996-01, Vol.16 (7), p.615-623

1996

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Modeling thermodynamics and phase equilibria for aqueous solutions of trisodium phosphate

Journal of solution chemistry, 1999-11, Vol.28 (11), p.1207-1238

1999

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The neptunium-iron phase diagram

Journal of nuclear materials, 1994-08, Vol.211 (3), p.215-222

1994

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Recovery of Fissile Materials from Wastes and Conversion of the Residual Wastes to Glass

Nuclear technology, 1998-09, Vol.123 (3), p.341-349

1998

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A Solubility Model for Aqueous Solutions Containing Sodium, Fluoride, and Phosphate Ions

Industrial & engineering chemistry research, 2000-02, Vol.39 (2), p.518-526

2000

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Thermochemical Modeling of Glass: Application to High-Level Nuclear Waste Glass

MRS bulletin, 1999, Vol.24 (4), p.37-44

1999

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Partial oxygen pressure and temperature effects on the oxygen content of the Y–Ba–Cu–O melts

Physica. C, Superconductivity, 1998-06, Vol.302 (2), p.130-136

1998

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Organic Iodide Formation During Severe Accidents in Light Water Nuclear Reactors

Nuclear technology, 1987-07, Vol.78 (1), p.34-42

1987

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DISSOLUTION OF ORNL HLW SLUDGE AND PARTITIONING OF THE ACTINIDES USING THE TRUEX PROCESS

Separation science and technology, 1999-01, Vol.34 (6-7), p.1021-1042

1999

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Tellurium Behavior in Containment under Light Water Reactor Accident Conditions

Nuclear technology, 1987-09, Vol.78 (3), p.295-302

Beahm, Edward C.

1987

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Optimal determination of rate coefficients in multiple-reaction systems

Computers & chemistry, 1992-10, Vol.16 (4), p.325-333

1992

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Fission Product Transport Behavior

Nuclear technology, 1993-03, Vol.101 (3), p.262-269

1993

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Iodine Partitioning in Pressurized Water Reactor Steam Generator Accidents

Nuclear technology, 1990-04, Vol.90 (1), p.16-22

1990

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Assessment of Nepheline Precipitation in Nuclear Waste Glass Via Thermochemical Modeling

MRS proceedings, 1999-12, Vol.608 (1), Article 715

1999

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Thermochemical Models for Nuclear Waste Glass Subsystems – MgO-CaO and MgO-Al2O3

MRS proceedings, 1999, Vol.556

1999

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Partial oxygen pressure and temperature effects on the oxygen content of the Y-Ba-Cu-O melts

Physica. C, Superconductivity, 1998, Vol.302 (2-3), p.130-136

1998

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Thermochemical Models for Nuclear Waste Glass Subsystems – MgO-CaO and MgO-Al 2 O 3

MRS proceedings, 1999, Vol.556, Article 383

1999

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Thermochemical Models for Nuclear Waste Glass Subsystems: MgO-CaO and MgO-Al sub(2)O sub(3)

MRS proceedings, 1998-11, Vol.556, p.383-383

1998

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Dissolution of ORNL HLW sludge and partitioning of the actinides using the TRUEX process

Separation science and technology, 1997-10, Vol.34 (6-7), p.1021-1042

1997

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Direct Conversion of Halogen-Containing Wastes to Borosilicate Glass

MRS proceedings, 1996, Vol.465, Article 131

1996

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Basic Compatibility Studies of Advanced Fuels with 3d Transition Metals

Nuclear technology, 1977-08, Vol.35 (1), p.173-177

1977

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Matrix isolation and decay kinetics of carbon dioxide and carbonate anion free radicals

Journal of physical chemistry (1952), 1970-08, Vol.74 (17), p.3225-3231

1970

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Laves phases of uranium and 3d transition metals

Journal of the less-common metals, 1976-01, Vol.50 (1), p.57-71

1976

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Fission product transport behavior: Severe accident technology

Nuclear technology, 1993, Vol.101 (3), p.262-269

1993

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Appendix. Description of variables used in the solgasmix program

Calphad, 1983-01, Vol.7 (2), p.103-111

1983

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Conversion of radioactive and hazardous chemical wastes into borosilicate glass using the glass material oxidation and dissolution system

Modeling thermodynamics and phase equilibria for aqueous solutions of trisodium phosphate

The neptunium-iron phase diagram

Recovery of Fissile Materials from Wastes and Conversion of the Residual Wastes to Glass

A Solubility Model for Aqueous Solutions Containing Sodium, Fluoride, and Phosphate Ions

Thermochemical Modeling of Glass: Application to High-Level Nuclear Waste Glass

Partial oxygen pressure and temperature effects on the oxygen content of the Y–Ba–Cu–O melts

Organic Iodide Formation During Severe Accidents in Light Water Nuclear Reactors

DISSOLUTION OF ORNL HLW SLUDGE AND PARTITIONING OF THE ACTINIDES USING THE TRUEX PROCESS

Tellurium Behavior in Containment under Light Water Reactor Accident Conditions

Optimal determination of rate coefficients in multiple-reaction systems

Fission Product Transport Behavior

Iodine Partitioning in Pressurized Water Reactor Steam Generator Accidents

Assessment of Nepheline Precipitation in Nuclear Waste Glass Via Thermochemical Modeling

Thermochemical Models for Nuclear Waste Glass Subsystems – MgO-CaO and MgO-Al2O3

Partial oxygen pressure and temperature effects on the oxygen content of the Y-Ba-Cu-O melts

Thermochemical Models for Nuclear Waste Glass Subsystems – MgO-CaO and MgO-Al 2 O 3

Thermochemical Models for Nuclear Waste Glass Subsystems: MgO-CaO and MgO-Al sub(2)O sub(3)

Dissolution of ORNL HLW sludge and partitioning of the actinides using the TRUEX process

Direct Conversion of Halogen-Containing Wastes to Borosilicate Glass

Basic Compatibility Studies of Advanced Fuels with 3d Transition Metals

Matrix isolation and decay kinetics of carbon dioxide and carbonate anion free radicals

Laves phases of uranium and 3d transition metals

Fission product transport behavior: Severe accident technology

Appendix. Description of variables used in the solgasmix program

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