AEET-CD/7, Studies in Electrolytic Reduction of Uranium (VI) in Alkaline Media, A.D. Damodaran, 1962

AEET-ANAL-5, Volumetric Determination of Uranium After its Separation By Tributylphosphate Extraction, L.M. Mahajan, 1963

BARC-374, Trilaurylamine as an Extracting Agent for the Final Purification of Plutonium During the Reprocessing of Irradiated Fuel, N. Srinivasan, 1968

BARC-375, Studies on the Use of Uranium (IV) as a Reductant for Plutonium in PUREX Process, N. Srinivasan,1968

BARC-384, Some Studies on the Radiation Chemistry of Tridodecylamine, P.K. Bhattacharyya,1968

BARC-397, Laboratory Investigations on Direct Chlorination Volatility Processing of Nuclear Fuels. Part I, S.P. Sood, 1969

BARC-476, The Use of Trilaurylamine as an Extracting Agent for Plutonium (IÍV), S.V. Kumar, 1970

BARC-404, Laboratory Investigations on Direct Chlorination Volatility Processing of Nuclear Fuels. Part II, S.P. Sood, 1969

BARC-405, Laboratory Investigations on Direct Chlorination Volatility Processing of Nuclear Fuels. Part III, S.P. Sood, 1969

BARC-406, Laboratory Investigations on Direct Chlorination Volatility Processing of Nuclear Fuels. Part IV, R. Prasad, 1969

BARC-428, Process Chemistry of Neptunium. Part I N. Srinivasan, 1969

BARC-430, Application of Uranous Nitrate as a Reductant for the Separation of Plutonium from Uranium in the Partitioning Column R.T.Chitnis, 1969

BARC-432, Co-Extraction Studies of Uranium and Plutonium with Tributyl Phosphate in Nitric Acid Media, N. Srinivasan, 1969

BARC-433, In-Line Analysis of Fuel Reprocessing Streams: A Review, V.K. Bhargava, 1969

BARC-589, Pilot Plant Studies with a Pulsed Solvent Extraction Column, N. Srinivasan, 1972

BARC-636, Extraction of Neptunium by Trilaurylamine, S.K. Patil, 1972

BARC-643, Pilot Plant for the Separation of U-233 at TROMBAY, N. Srinivasan, 1972

BARC-659, Trilaurylamine as an Extracting Agent for the Final Purification of Plutonium During the Reprocessing of Irradiated Fuel. A Literature Survey, G.M. Nair, 1973

BARC-662, In-Line Analytical Methods for Fuel Reprocessing Streams. Part III: Gamma Monitoring of Fission Products, S.G. Marathe, 1973

BARC-668, Studies on Application on Airlift in Fuel Reprocessing Engineering, A.N. Prasad,1973

BARC-672, Development of Air Pulsed Mixer Settler Equipments for Solvent Extraction Studies, N. Srinivasan, 1973

BARC-673, Laboratory Counter Current Extraction and Stripping Studies in Air Pulsed Mixer Settler Battery for High Plutonium Concentrations, N. Srinivasan, 1973

BARC-681, Laboratory Studies on Acid THOREX Process, N. Srinivasan, 1973

BARC-690, Process Chemistry in Neptunium, N. Srinivasan, 1973

BARC/I-253, Pilot Plant Studies With Mixer Settlers, G.R. Balasubramanian, 1973

BARC-728, Studies on the Tail End Purification of Uranium in the PUREX Process, S.V. Kumar, 1974

BARC-730, Extraction of Actinides by Some Long-Chain Amines, R. Swarup, 1974

BARC-731, Application of the Weak Base Anion Exchange Resin Amberlite XE-270 for Recovery of Uranium from Sulphate Leach Solutions: A Preliminary Study, K.D. Kamat, 1974

BARC-733, Design of an Air Pulser for Solvent Extraction Columns, S.V. Kumar, 1974

BARC-734, Counter-Current Extraction Studies for the Recovery of Neptunium by the PUREX Process. Part I, N. Srinivasan, 1974

BARC-735, Counter-Current Extraction Studies for the Recovery of Neptunium by the PUREX Process. Part II, N. Srinivasan, 1974

BARC-736, Process Chemistry of Neptunium Part III, N. Srinivasan, 1974

BARC-780, Separation of Uranium and Thorium on Ammonium Phosphotungstate in Nitric Acid, M.N. Nadkarni, 1974

BARC-781, Destruction of Nitric Acid in PUREX Process Streams by Formaldehyde Treatment ,S.V. Kumar,1974

BARC-782, Use of Reductants in the Purification of Uranium by PUREX Process ,S.V. Kumar,1974

BARC-790, In-Line Analytical Methods for Fuel Reprocessing streams. Part IV. Neutron Monitoring for Plutonium ,V.K. Rao,1975

BARC-885, Extraction of Tetravalent and Hexavalent Actinide Ions by Tetraheptylammonium Nitrate ,R. Swarup,1977

BARC-893, Studies on Inorganic Exchangers - Ammonium Phosphomolybdate (AMP) and Ammonium Phosphotungtate (APW) ,T.S. Murthy ,1977

BARC-894, Studies on Inorganic Exchangers - Polyantimonic Acid, T.S. Murthy,1976

BARC-899, Exchange of Th, U, and Pu on Macroporous Ion Exchange Resins, M.N. Nadkarni,1977

BARC-907, Aqueous Coordination Complexes of Neptunium ,S.K. Patil,1976

BARC-912, Study of Plutonium (IV) Elution from Macromolecular Anion Exchange Resin by 0.5 M Nitric Acid ,M.N. Nadkarni,1976

BARC-913, Separation and Purification of Uranium by Ion Exchange on Stannic Phosphate ,P.C. Mayankutty,1977

BARC-915, Studies on Inorganic Ion-Exchangers. Part I: Application of Polyantimonic Acid for the Polishing of Uranium Product of Reprocessing Stream ,T.S. Murthy, 1977

RRC-17,Backmixing Studies in a Pulsed Extraction Column-Part 1: Single Phase Flow ,G.R. Balasubramanian ,1977

BARC-928, Ion Exchange in Organic Solvents. Part I: Absorption of Thorium, Uranium, and Plutonium by Macroreticular Ion Exchangers from Tri-n- Butyl Phosphate ,P.C. Mayankutty,1977

BARC-933, Separation of Tributyl Phosphate from Degraded Solvents ,S.V. Kumar,1977

BARC-939, Ion Exchange Separation of Lead and Neodymium from a Solution of Irradiated Nuclear Fuel ,K.L. Ramakumar,1977

BARC-940, Laboratory Studies on the Recovery of Uranium-233 From Irradiated Thorium by Solvent Extraction Using 5% TBP Shell Sol-T as Solvent ,G.R. Balaubramaniam,1977

BARC-952, Effect of Temperature on the Extraction of Uranium (VI) from Nitric Acid by Tri-n-Butyl Phosphate, S.V. Bagawde,1978

BARC-982, Formation of Secondary Amine in the Radiolysis of Trilaurylamine, P.K. Bhattacharyya,1978

BARC-986, A Passive Gamma Scanner for Estimation of Plutonium in Fabrication Waste, P. Prasanna,1978

BARC-991, Studies on the Effect of Temperature and Complexing Agents on the Stripping of Uranium in PUREX Process ,A. Ramanujam,1979

BARC-1003 ,Cation Exchange Separation of Uranium from Thorium, R.T. Chitnis ,1979

BARC-1006,Anion Exchange Separation and Purification of Neodymium from Fission Products ,R.T. Chitnis,1979

BARC-1007,Spectrophotometric Studies on the Formation of Adducts Involved in Synergistic Extraction of Uranium(IV) By Mixtures of HTTA and Neutral Donors ,S.K. Patil,1979

BARC-1008,Ion Exchange Studies with Ferrocyanide Molybdate and Zirconium Phosphate in Mixed Solvent Media.Part I: Synthesis of the Exchangers ,M. Ramaswamy,1979

BARC-1039,Counter-Current Extraction Studies for the Recovery of Neptunium by the PUREX Process,S.V. Kumar,1979

BARC-1046,Isotope Dilution Alpha Spectrometry for the Determination of Plutonium Concentration in Irradiated

Fuel Dissolver Solution: IDAS and R-IDAS,M.V. Ramaniah,1980

BARC-1090,Synergistic Extraction of Actinides: Part I. Hexa-and Pentavalent Actinides,S.K. Patil,1980

BARC-1101,Some Aspects of Synergistic Extraction of Actinides and Lanthanides from Mixed Aqueous-Organic Media,J.P. Shukla,1981

BARC-1108,Synergistic Extraction of Actinides: Part II.Tetra-and Trivalent Actinides ,S.K. Patil,1981

BARC-1142,Recovery of Uranium from Solutions Containing High Concentrations of Fluoride ,M.S. Subramanian ,1982

BARC-1188,Development of a Dry Recycling Route for Rejected UO₂ and UO₂ -4 Wt. % PuO₂ Sintered Pellets ,H.S. Ramatn, 1983

BARC-1272,Chromatographic Assay of Degradation Products of Tributyl Phosphate, S.C. Tripathi,1985

BARC-1318,Synthesis and Characterization of Aliphatic Long- Chain Sulfoxides ,M.S. Nagar,1986

BARC-1370,Method for the Purification and Estimation of Milligram Amounts of Thorium-229 from Bulk Uranium-233

A. Ramaswami,1988

(See CONF-711009-5, R.H. Rainey, ORNL, Separation of Daughters of U-232 from U-233 by Ion Exchange, see also U. S. Patent Appl. 722,023, 1986, G.G. Briggs, Process for Reducing Beta Activity in Uranium for related information)

BARC-1380,Mono-Octylphenyl Phosphoric (MOPPA) as an Extractant for Plutonium ,P.D. Mithapara ,1987

BARC-1422,Continuous Process for Precipitation of Ammonium Diuranate from Uranyl Solution: Part I ,I.A. Siddiqui,1988

BARC-1480,Treatment of Tributyl Phosphate Wastes by Extraction and Pyrolysis Process ,D.S. Deshingkar,1989

BARC-1482,Purification of Degraded TBP Solvent Using Macroreticular Anion Exchange Resin,P.K. Kartha,1989

BARC-1486,Separation and Purification of Uranium Product from Thorium in THOREX Process by Precipitation Process, A. Ramanujam,1989

BARC/I-986,New Extractants for the Separation and Purification of Actinides,M.S. Murali,1989

BARC-1499,Data Processing Software for PUREX Plant Control Laboratory,V.P. Kansara,1990

BARC-1512,Studies on the Sorption Behavior of Plutonium and Fission Products on Stannic Antimonate,I.C. Thambi,1990

BARC-1515,Monitoring of Plutonium in High Active Waste Streams of PUREX Process by Alpha Spectrometry,P.V. Achuthan,1990

BARC-1530,Recovery of Americium from Slag and Crucible Wastes and its Purification, K.M. Michael,1990

BARC-1535,Identification of Resin Degradation Product, P.S. Dhami,1990

BARC-1539,Direct Spectrophotometer Method for the Determination of Microgram Quantities of Uranium with Bromo-PADAP in Aqueous and Organic Waste Streams of PUREX and THOREX Processes ,S.K. Das, 1991

BARC-1991/E/002,Analytical Techniques for In-Line/On-Line Monitoring of Uranium and Plutonium in Process Solutions: A Brief Literature Survey,S.G. Marathe,1991

BARC-1991/E/003, Study of Pneumatic Filter for Feed Clarification in Reprocessing Plant Head-End,I.A. Siddiqui, 1991

BARC-1991/E/009 Separation and Purification of Short Lived Fission Products from Irradiated Uranium,R.R. Balasubramanian,1991

BARC-1991/E/018 Studies on Resin Degradation Products Encountered During Purification of Plutonium by Anion Exchange, A. Ramanujam,1991

BARC-1992/E/002, Role of Ion Exchange Membrane in the Production of Uranous Nitrate,M.K.I. Nair,1992

BARC-1992/E/007,Synthesis and Characterization of Some Aliphatic Monoamides and Diamides,P.B. Ruikar,1992

BARC-1992/E/009 Extraction of Actinides from High Level Waste Streams of PUREX Process Using Mixtures of CMPO and TBP in Dodecane ,J.N. Mathur,1992

BARC-1992/E/013, Studies on Inorganic Exchangers: Zirconium Antimonate, A. Dash, 1992

BARC-1992/E/045, Studies on Inorganic Exchangers: Hydrous Manganese (II) Oxide, C. Mathew, 1992

BARC-1993/E/013, Recovery of Plutonium From Oxalate Bearing Solutions Using a Mixture of CMPO and TBP, J.N. Mathur, 1993

BARC-1993/E/024, Application of Extraction Chromatographic Technique in the Recovery of Actinides from Purex Waste Solutions Using CMPO, A. Ramanujam, 1993

BARC-1993/E/027, Determination of Trace Elements inPlutonium by Solvent Extraction and ICP - Atomic Emission, Spectroscopy, A.B. Patwaedham, 1993

BARC-1993/E/029, Studies on the Separation of Thorium and Uranium on Variously Crosslinked DOWEX 50W Resins, P.V. Achuthan, 1993

BARC-1993/E/035, Counter Current Studies on Actinide Partitioning From Sulfate Bearing Simulated High Level Waste Using CMPO, D.S. Deshingkar, 1993

BARC-1994/E/006, Some Aspects of the Extraction Separation of Actinides by Macrocyclic Crown Compounds, R.K. Singh, 1994

BARC-1994/E/008, Studies on the Solvent Extraction Behavior of Pu(IV) from Nitric Acid, Nitric-Perchloric Acid, and Hydrochloric Acids, by Di,2-Ethylhexyl Phosphoric Acid (HDEHP), S.K. Kannan, 1994

BARC-1994/E/012 Removal of Radioruthenium from Alkaline Intermediate Level Radioactive Waste Solution: A Laboratory Investigation, S.K. Samanata, 1994

BARC-1994/E/014, Partitioning of Actinide From Simulated High Level Waste Arising From Reprocessing of PHWR Fuels: Counter Current ExtractionStudies Using CMPO

BARC-1994/E/019, Alkaline Hydrolysis Process for Treatment and Disposal of PUREX Solvent Waste, C. Srinivas, 1994

BARC-1994/E/023, Tributylphosphate Process for Actinide Partitioning from High Level Wastes, R.R. Chitnis, 1994

BARC-1994/E/024, Dicylcohexano-18-crown-6 as a Novel carrier in the Liquid Membrane Permeation of Actinides, A. Kumar, 1994

BARC-1994/E/041, Wet Oxidative Destruction of Spent Ion-Exchange Resins Using Hydrogen Peroxide, C. Srinivas, 1994

BARC-1995/E/011, Partitioning and recovery of Neptunium From High Level Waste Streams of PUREX Origin Using 30% TBP, J.N. Mathur, 1994

Conference Papers:

International Conference on the Peaceful Uses of Nuclear Energy, 1964, (A/CONF.28/P/786), H.N. Sethna, Fuel Reprocessing Plant at Trombay

International Conference on the Peaceful Uses of Nuclear Energy, 1964, (A/CONF.28/P/787), A.S. Mazumdar , Chemistry of Separation of Plutonium from Irradiated Fuel

Radiation Technology and Applied Nuclear Chemistry, Madras, India, 1971, N. Srinivasan, Observations on the Process Chemistry of Neptunium

Seminar on Radiation Damage in Reactor Materials, Bombay, India, 1972, S.E. Britto, Radiation Damage of the Organic Solvent in the Extraction Process of Fuel Reprocessing

Physical Methods in Structural Inorganic Chemistry, Actinide Chemistry and Solid State Studies, Bombay, India, 1972, S.K. Patil, Process Chemistry of Neptunium - Counter Current Extraction Studies for the Coextraction of Neptunium in the PUREX Process

30th Session of Indian Institute of Chemical Engineers, Chandigar, India, 1977, S. Nagarajan, Development and Performance of Centrifugal Contactor Suitable for Nuclear Fuel Reprocessing

Nuclear Power and its Fuel Cycle, 1977, Salzburg, Austria, A.N. Prasad, Indian Experience in Fuel Reprocessing

Nuclear Safeguards Technology, 1978, Vienna, Austria, C.K. Mathews, Tracer Techniques in the Input Accountability of Plutonium in Reprocessing Plants, Symposium of Solvent Extraction of Metals, Bombay, India, 1979, S.B. Koganti, Development of Centrifugal Contactor

Symposium of Solvent Extraction of Metals, Bombay, India, 1979, M. Venkataraman, Development of Air Pulsed Mixer Settler

Symposium of Solvent Extraction of Metals, Bombay, India, 1979, S.V. Kumar, Counter-Current Extraction Studies for the Recovery of Neptunium in the PUREX Process: Part III

Symposium of Solvent Extraction of Metals, Bombay, India, 1979, A. Ramanujam, Utilization of Laboratory Mixer Settlers for Solvent Extraction Flowsheet Studies

33rd Session of Indian Institute of Chemical Engineers, Dehli, India, 1980, M.S. Ilangovan, Metering of Radioactive Liquids for Feeding to Various Solvent Extraction Contactors

International Conference on Fast Reactor Fuel Cycle, London, 1981, G.R. Balasubramanian, Reprocessing of Fast Reactor Fuel and the Indian Approach to It

34th Annual Session of Chemical Engineers, Madras, India, 1981, S.A.K. Jeelani, Feed Clarifiaction Studies in Nuclear Fuel Reprocessing

Radiochemistry and Radiation Chemistry Symposium, Pune, India, 1982, M.S. Oak, Some Observations on the Oxidation of Plutonium to Plutonium(VI) With Hydrogen Peroxide in the Presence of Iron(II)

Radiochemistry and Radiation Chemistry Symposium, Pune, India, 1982, A. Mukherjee, Anion Exchange Separation of Uranium from Thorium for the Tail-End Purification of ²³³U in Thorex Process

International Solvent Extraction Conference, Denver, CO, 1983, S.B. Koganti, New Extraction Equipment for Nuclear Fuel Reprocessing Application

International Solvent Extraction Conference, Denver, CO, 1983, M.S. Ilangovan, Metering of Radioactive Liquids for Feeding to Various Solvent Extraction Contactors

Fuel Reprocessing and Waste Management, Jackson, Wyoming, 1984, P.G. Selvaraj, Development of Equipment for Fast Reactor Fuel Reprocessing

Proceedings of the Seminar on Remote Handling Equipment for Nuclear Fuel Cycle Facilities, Oxford, UK, 1984, P. Ramkumar, Role of Remote Handling in the Fast Reactor Fuel Reprocessing Programme in India

Proceedings of the Fifth Pacific Basin Nuclear Conference, Seoul, South Korea, 1985, A.N. Prasad, Spent Fuel Transport and Reprocessing

Radiation and radiochemistry Symspoium, Tirupati, India, 1986, M. Venkatesan, Some Studies on Plutonium Uranium Distribution in FBTR Fuel Reprocessing

ISEC '86 International Solvent Extraction Conference, 1986, S.B. Koganti, Development of Low Capacity Centrifugal Extractors for Small Scale Reprocessing Facilities

Back End of the Nuclear Fuel Cycle: Strategies and Options, Vienna, Austria, 1987, p561-2, D.D. Sood, Chemical Investigations Relevant to Plutonium Recycling

Radiochemistry and radiation Chemistry Symposium, Bombay, India, 1988, R.T. Kulkarni, Separation and Purification of ²³³U From Boron and Other Impurities

Symposium on Post Irradiation Examination in Nuclear Power Program, Bombay, 1989, H.D. Purandare, A Comparison of Experimental and Theoretical Plutonium Isotopic Values for Fuel Discharged from RAPS-1

Symposium on Post Irradiation Examination in Nuclear Power Programme, Bombay, 1989, V.P. Sharma, Remotely Operated Dismantling Device for PIE of Dhruva Reactor Fuel

Symposium on Uranium Technology, Bombay, 1989, S.K. Misra, Uranyl Ion Transport Across Tri-n-Butyl Phosphate/n-Dodecane Liquid Membranes

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, D.G. Phat, Nature of Pu(IV) Complex Extracted by D₂EHPA - A Structure Evaluation

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, V.B. Sagar, Studies on the Recovery of U²³³ from Phosphate Containing Analytical Waste Using DBDECMP as Extractant

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, G. Chourasiya, Isotope Abundances of Plutonium in Dissolver Solution of Irradiated Fuel by Alpha Spectroscopy

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, P.D. Mithapara, Studies on the Synergistic Effects on the Extraction of Plutonium (IV) by Mono-Octylphenyl Phosphoric Acid

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, P.R. Sangurdekar , Effect of Radiation on the Solvent Extraction of Metals

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, K. Vijayan, Flow Sheet for the Recovery of Plutonium and Uranium from Scraps of Mixed Oxide Fuel Fabrication

DAE Symposium on Radiochemistry and Radiation Chemistry, Klapakkam, 1989, G.M. Dabholkar, Recovery of Plutonium from Slag and Crucibles by Solvent Extraction

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, D.S. Divakar, Simulation Studies of Counter Current Extraction of Plutonium in 20% Tri-n-Butyl Phosphate for the Proposed Plutonium Purification Cycle in a Reprocessing Plant

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, K.K. Gupta, Simultaneous Determination of Free Acid and Uranium (VI) in Purex Process Streams

DAE Symposium on Radiochemistry and Radiation Chemistry, Kalpakkam, 1989, A.D. Moorthy, On-Line Measurement of Plutonium in Product Solution in Reprocessing Plant

Indo-Japan Seminar on Thorium Utilization, Bombay, India, 1990, A. Ramanujam, Experience in Final Separation, Purification and Recycling of Uranium-233

Indo-Japan Seminar on Thorium Utilization, Bombay, India, 1990, G.R. Balsaubramanian, Reprocessing of Irradiated Thorium: Indian Experience

Proceedings of the Symposium on Advanced Remote Handling Systems and Automation in Nuclear Installations (ROSYMP-90), Bombay, India, 1990, P. Seetharamaiah, Experience in Remote Handling and Automation for Spent Fuel Handling System and Head End Treatment in Fuel Reprocessing Plants

Proceedings of the Symposium on Advanced Remote Handling Systems and Automation in Nuclear Installations (ROSYMP-90), Bombay, India, 1990, A. Ravishankar, Operating Experience With Remote Hnadling Equipment in a Typical Hot Facility

International Symposium on Radiochemistry and Radiation Chemistry (Plutonium-50 years), Bombay, India, 1991, P.S. Dhami, Studies on the Degradation of Anion Exchanger Employed for Plutonium Purification

International Symposium on Radiochemistry and Radiation Chemistry (Plutonium-50 years), Bombay, India, 1991, J.P. Shukla, Liquid-Liquid Extraction of Americium(III) by Bis(2-Ethylhexyl)Sulfoxide From Aqueous Nitrate Media

International Symposium on Radiochemistry and Radiation Chemistry (Plutonium-50 years), Bombay, India, 1991, R.K. Singh, Studies on Polishing of Degraded PUREX Solvent for Partial Recycle

International Symposium on Radiochemistry and Radiation Chemistry (Plutonium-50 years), Bombay, India, 1991, A. Palamalai, Electro-Oxidative Destruction of Organic Wastes Generated in a Reprocessing Plant

International Symposium on Radiochemistry and Radiation Chemistry (Plutonium-50 years), Bombay, India, 1991, P.B. Gurba, Electro-Oxidative Decomposition of Alpha Contaminated Ion Exchange Resin

Third International Conference on Nuclear Fuel Reprocessing and Waste Management, 1991, Vol. 1, p64-8, M.K.T. Nair, Back-End of the Nuclear Fuel Cycle - Indian Experience

Third International Conference on Nuclear Fuel Reprocessing and Waste Management, 1991, Vol. 2, p839-53, G.R. Balasubramanian, Fire Safety in Nuclear Fuel Reprocessing Plants

Third International Conference on Nuclear Fuel Reprocessing and Waste Management, 1991, Vol. 2, p1090-4, G.R. Balasubramanian, Separation of U²³³ from Irradiated Thorium - Indian Experience

Proceedings of the Symposium on Zirconium Alloys for Reactor Components, Bombay, India, 1992, M. Chandran, Experience in Chopping Zircaloy Clad PHWR Spent Fuels at Reprocessing Plant, Tarapur

Proceedings of National Symposium on Computer Applications in Power Plants, 1992, Bombay, India, G.K. Padmashali, Computer Controlled Robotized On-Line Sampling System in Fuel Reprocessing

Proceedings of National Symposium on Computer Applications in Power Plants, 1992, Bombay, India, S. Kumar, An Expert System for Real-Time Diagnostics of a Fast Reactor Fuel Reprocessing Plant

Proceedings of the Institution of Mechanical Engineers. The Management of Irradiated Nuclear Fuel, Manchester, UK, 1992, N. Ramnath, Transportation, Handling, and Processing of Irradiated Thorium Rods

Nuclear and Radiochemistry Symposium, Visakhapatnam, India, 1992, S.C. Tripathi, GLC Detection of Higher Molecular Weight Organophosphorus Compound in Radiolytically Degraded 30%TBP/n-Dodecane/HNO₃ System

Nuclear and Radiochemistry Symposium, Visakhapatnam, India, 1992, P.G. Kulkarni, Extraction of Uranium(VI) From Nitirc Acid Medium With TBP-Duolite-S-861 Resin

Nuclear and Radiochemistry Symposium, Visakhapatnam, India, 1992, M. Venkatesan, Laboratory Studies on the Tail End Purification of U-233 From Thorium in Electrolysis Technique

Nuclear and Radiochemistry Symposium, Visakhapatnam, India, 1992, A. Ramanujam, Studies on the Solubilities of Precipitates Formed by Thorium and Plutonium With Resin Degradation Products

Nuclear and Radiochemistry Symposium, Visakhapatnam, India, 1992, G.A. Chaugule, Mixed Solvent Extractants for Prevention of Plutonium Accumulation in the Counter Current Extraction Columns

Proceedings of the 10th National Conference of the Indian Membrane Society, Bombay, India, 1993, R.K. Singh

Feasibility Studies on the Reprocessing of Material Test Reactor (MTR) Fuel Using Membrane Cell

Proceedings of the International Conference and Technology Exposition on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options, Seattle, WA, 1993, J. Mathur, Partitioning of Actinides from Acid Waste Solutions of PUREX Origin Using CMPO

Proceedings of the International Conference and Technology Exposition on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options, Seattle, WA, 1993, G.S. Murthy, Isolation of Cesium from Fission Product Solution on New Complex Inorganic Exchangers

Safety and Environmental Aspects of Partitioning and Transmutation of Actinidies and Fission Products, Vienna, Austria, 1993, A. Ramanujam, Partitioning of Actinides From Acid Waste Solutions of the PUREX Process by Solvent Extraction and Extraction Chromatography

National Symposium on Electrochemistry in Nuclear Technology, Kalpakkam, 1994, H.P. Nawada, Therochemical Modeling of IFR Fuel by Electrorefining Process

Trombay Symposium on Radiation and Radiochemistry, Bombay, India, 1994, N.R. Jawahar, Studies on Radiation Stability of Interpolymer Cation Exchange Membranes

Symposium on Strategies Hi-Tech Metals Extraction Process Characteristics, Udaipur, 1994, H.P. Nawada, Numerical Simulation Studies in IFR Electrorefining

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, R.P. Raju, Dynamic Behavior of Solvent Contractors in Fuel Reprocessing Plants - An Analysis

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, B.C. Majee, Design and Development of a Digital Phase Ratio Meter

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, A.K. Kalburgi, Chemisorption of Uranium Hexafluoride on Sodium Fluoride Pellets

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, S. Manohar, Theoretical Treatment of Equilibrium Data and Evaluation of Diffusion Coefficients in Extraction of Uranium

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, I.C. Pius, Studies of Sorption of Plutonium on Inorganic Exchangers from Sodium Carbonate Medium

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, D.R. Ghadse, Studies on Removal of Plutonium From Oxalic Acid Containing Hydrochloric Acid Solutions

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, A.R. Kumar, Solvent Extraction Process Development for High Plutonium Fuel Cycles

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, J.P. Shukla, Recent Advances in Liquid Membranes and Their Applications in Nuclear Waste Processing: An Overview

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, H.P. Nawada, Numerical Simulation of Minor Actinide Recovery Behavior in Batch Processing of Spent Metallic Fuel by Electrorefining

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, S.K. Ghosh, Recovery of Uranium From Crude Uranium Tetrafluoride

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, M.K. Rao, Application of Electrochemical Techniques in Fuel Reprocessing - An Overview

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, S. Manohar, Theoretical Treatment of Equilibrium Data and Evaluation of Diffusion Coefficients in Extraction of Uranium

ACE - 94. Advances in Chemical Engineering in Nuclear and Process Industries, Bombay, 1994, C.V. Rajagopalan, Development of Air Pulsed Ejector Mixer Settlers of Different Capacities

Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Los Alamos, NM, 1995, C.R. Gopalakrishnan, Criticality Safety Analysis of a Small Reprocessing Plant for Fast Reactor Fuel - A Case Study

NUCAR-95: Nuclear and Radiochemistry Symposium, Kalpakkam, India, 1995, S.C. Tripathi, Effects of Recycling on Radiolytic Degradation of 30% TBP-n-Dodecane-HNO₃ System. Part II: Extraction Behavior of Plutonium

NUCAR-95: Nuclear and Radiochemistry Symposium, Kalpakkam, India, 1995, K.M. Michael, Purification of Americium From Plutonium Loading Effluents Using Solvent Extraction and Extraction Chromatography Technique

NUCAR-95: Nuclear and Radiochemistry Symposium, Kalpakkam, India, 1995, M. Venkatesan, Laboratory Studies on Restoring Solvent in PUREX Process

Seminar on Experience With Dilute Chemical Decontamination in Indian Nuclear Reactors, Kalpakkam, India, 1995, M. Chandra, Decontamination of Process-Cell Equipment at Fuel reprocessing Plant, Tarapur

NUCAR-97: Nuclear and Radiochemistry Symposium, Calcutta, India, 1997, A. Palamalai, Anion Exchange Process in Acetic Acid Medium as a Reconversion Method for Reprocessing J-Rods

NUCAR-99: Nuclear and Radiochemistry Symposium, Mumbai, India, 1999, A. Palamalai, Solvent Extraction Purification of Uranium From Thorium in the Product Solution of Thorex Process Employed for Recovery of Uranium-233 From Irradiated Thorium

NUCAR-99: Nuclear and Radiochemistry Symposium, Mumbai, India, 1999, P.M. Mapara, Studies on the Oxidation of Np(IV) to Np(V) in Nitric Acid

NUCAR-99: Nuclear and Radiochemistry Symposium, Mumbai, India, 1999, P.M. Mapara, Extraction of Neptunium From Nitirc Acid into 30% TBP-n-Dodecane

Papers:

Journal of Radioanalytical and Nuclear Chemistry, 1971, Vol. 8, p223-9, N. Srinivasan, Estimation of Neptunium in a Fuel Reprocessing Plant

Nuclear Instruments and Methods, 1973, Vol. 109, p453-9, R.H. Iyer, Application of the Fission Track Registration Technique in the Estimation of Fissile Materials: ²³⁵U-Content in Natural and Depleted Uranium Samples and Total Uranium in Solution

Journal of Inorganic and Nuclear Chemistry, 1974, Vol. 36, p3819- , P.K. Khopkar, Thiocyanate Complexing of Some Trivalent Actinides and Lanthanides

Nuclear Instruments and Methods, 1975, Vol. 127, p99-103, S.G. Marathe, A Gamma-Monitoring Assembly for the Analysis of Fission Products in Reprocessing Streams

Kerntechnik, 1976, Vol. 18, p207-9, S. Bhagwandas, Use of Silver-Impregnated Resin for Trapping of Radioactive Iodine

Journal of Inorganic and Nuclear Chemistry, 1977, Vol. 39, p2063- , P.K. Khopkar, Synergistic Extraction of Some Trivalent Actinides and Lanthanides by Theonyltrifluoracteone and Aliquat Chloride

Journal of Radioanalytical Chemistry, 1978, Vol. 42, p323- , S.A. Pai, Extraction of Plutonium (IV), Uranium (VI) and Some Fission Products by Di-n-Hexylsulfoxide

Journal of Radioanalytical Chemistry, 1978, Vol. 42, p349- , A. Ramanujam, Studies on HTTA Extraction of Tetravalent Actinides

Journal of Radioanalytical Chemistry, 1978, Vol. 47, p5-15, V.K. Bhargava, Separation of Heavier Rare Earths from Neutron Irradiated Uranium Targets

Nuclear Technology, 1979, Vol. 42, p297-303, C.K. Mathews, Tracer Techniques for the Input Accountability of Plutonium in Reprocessing Plants: MAGTRAP and LEADTRAP

Separation Science and Technology, 1979, Vol. 14, p749-55, R. Thiagarajan, Separation of Uranium and Plutonium from an Aqueous Solution Containing Phosphoric, Sulfuric, and Nitric Acids by Solvent Extraction

Separation Science and Technology, 1979, Vol. 14, p883-, J.P. Shukla, Solvent Extraction of Plutonium (IV), Uranium (VI), and Some Fission Products With Di-n-Octylsulfoxide

Separation Science and Technology, 1980, Vol.15, p1471-81,

K.L. Ramakumar, Separation and Purification of Magnesium, Lead, and Neodymium from Dissolver Solution of Irradiated Fuel

Journal of Nuclear and Inorganic Chemistry, 1981, Vol. 43, p1045- , S.A. Pai, Thermodynamics of Extraction of U(VI), Np(IV), and Pu(IV) With Some Long Chain Aliphatic Sulfoxides

Solvent Extraction and Ion Exchange, 1983, Vol. 1, p349-412, J.N. Mathur, Synergism of Trivalent Actinides and Lanthanides

Solvent Extraction and Ion Exchange, 1983, Vol. 1, p597-606, J.N. Mathur, Separation and Purification of Berkelium (III) From Trivalent Actinides and Lanthanides Using 1-Phenyl-3-Methyl-4-Benzoyl-Pyrazolone-5 (HPMBP)

Solvent Extraction and Ion Exchange, 1983, Vol. 1, p765-74, C.V. Karekar, Studies on the Extraction of Plutonium (IV) From Aqueous Nitric Acid - Oxalic Acid by Aliquat-336

Polyhedron, 1984, Vol. 3, p1125-9, J.N. Mathur, Extraction of Trivalent Actinides with Some Substituted Pyrazolones and their Synergistic Mixtures with Tri-n-Ocytlphoshine Oxide in Chloroform

Annalen der Chemie, 1984, Vol. 74, p461-9, S.K. Srivastava, Studies on the Exchange Properties of Thorium Hexacyanoferrate(II)

Separation Science and Technology, 1985, Vol. 20, p205-12, M. Subba Rao, Studies on the Absorption of Americium on Alumina From Aqueous Nitric Acid-Oxalic Acid Solutions

Solvent Extraction and Ion Exchange, 1985, Vol. 3, p753-62, J.N. Mathur, Ion Exchange Behavior of Chelating Resin Dowex A-1 With Actinides and Lanthanides

Radiochemica Acta, 1986, Vol. 40, p151-4, T.G. Srinivasan, Third Phase Formation in the Extraction of Plutonium by Tri-n-Butyl Phosphate

Nuclear Technology, 1986, Vol. 75, p332-7, E. Zimmer, Crud Formation in the PUREX and THOREX Processes

Solvent Extraction and Ion Exchange, 1986, Vol. 4, p969-85, C.R. Panda, Liquid-Liquid Extraction of Pa(V)and Zr(IV) by Mixtures of a B-Diketone and a Sulfoxide From Hydrochloric Acid Media

Nuclear Technology, 1987, Vol. 78, p69-74, K. Chander, Direct Dissolution of Nuclear Materials for Chemical Quality Control

Nuclear Technology, 1987, Vol. 79, p116-9, A.M. Shakila, Dissolution of PuO₂ in HNO₃/HF/N₂H₄ Medium

Transactions of the SAEST, 1987, Vol. 22, p215-8, A. Palamalai, Electrolytic Destruction of Nitric Acid in Simulated PUREX Process Streams

Journal of Radioanalytical and Nuclear Chemistry, 1988, Vol. 120, p65-73, M.S. Singh, Liquid-Liquid Extraction of Th⁴⁺ and UO₂2+ by LIX-26 and Its Mixtures

Solvent Extraction and Ion Exchange, 1988, Vol. 6, p111-24, J.N. Mathur, Use of Crown Ethers as Synergists in the Solvent Extraction of Trivalent Actinides and Lanthanides by 1-Phenyl-3-Methyl-4-Trifluoroacetyl-Pyrazolone-5

Journal of Radioanalytical and Nuclear Chemistry Articles, 1988, Vol. 120, p401-5, S.K. Saha, A Method for the Purification of Bulk Amount of Thorium from its Daughter Products

Journal of Radioanalytical and Nuclear Chemistry Articles, 1988, Vol. 121, p137-42, S. Singh, Solvent Extraction of Uranium (VI) by LIX-54 and its Mixtures

Journal of Radioanalytical and Nuclear Chemistry Articles, 1988, Vol. 121, p149-59, K.V. Chetty, Some Studies on Synergic Extraction of Mixed Ligand Species of Uranium (VI)

Journal of Radioanalytical and Nuclear Chemistry Articles, 1988, Vol. 122, p137-42, S. Singh, Solvent Extraction of Uranium (VI) by LIX-54 and its Mixtures

Separation Science and Technology, 1988, Vol. 23, p1401-8, T.G. Srinivasan, Effect of Uranium on Third Phase Formation in the Pu(IV)-HNO₃-TBP-Dodecane System

Journal of Radioanalytical and Nuclear Chemistry Articles, 1990, Vol. 139, p121-, V.B. Sagar, Studies on the Recovery of U²³³ from Phosphate Containing Nitric Acid Solutions Using DBDECMP as Extractant

Journal of Radioanalytical and Nuclear Chemistry Articles, 1990, Vol. 150, p473- , P.B. Ruikar, Extraction of Uranium (VI) and Plutonium (IV) With Some Aliphatic Amides

Solvent Extraction and Ion Exchange, 1990, Vol. 8, p629-41, J. N. Mathur, Thermodynamics of Am³⁺-Subsituted Pyrazolone-Crown Ether Adducts

Radiochemica Acta, 1991, Vol. 55, p29-35 , A. Palamalai, Development of an Electro-Oxidative Dissolution Technique for Fast Reactor Carbide Fuels

Polyhedron, 1991, Vol. 10, p47- , J.N. Mathur, Complexation and Thermodynamics of the Uranyl Ion With Phosphate

Solvent Extraction and Ion Exchange, 1991, VOl. 9, p337-81, N.R. Das, Liquid Ion Exchangers and Their Uses in the Separation of Zirconium, Niobium, Molybdenum, Hafnium, Tantalum and Tungsten

Journal of Radioanalytical and Nuclear Chemistry Articles, 1991, Vol. 152, p479-86, M.M. Charyulu, The Behavior of Plutonium in Aqueous Basic Media

Radiochemica Acta, 1992, Vol. 56, p21-, J.P. Shukla, Solvent Extraction of Plutonium (IV) into Dodecane by Bis(2-ethylhexyl)sulfoxide From Mixed Aqueous-Organic Solutions

Journal of Radioanalytical and Nuclear Chemistry Articles, 1992, Vol. 162, p171-, J.N. Mathur, Uptake of Actnides and Lanthanides from Nitric Acid by Dihexyl-N,N-Diethylcarbomylmethylphosphonate Adsorbed on Chromosorb

Journal of Radioanalytical and Nuclear Chemistry Articles, 1992, Vol. 162, p219-27, J.N. Mathur, Tail-End Purification of Americium From Plutonium Loading Effluents Using a Mixture of Octyl(Phenyl)-N,N,-Diisobutylcarbamoylmethylphosphine Oxide and Tri-n-Butyl Phosphate

Journal of Radioanalytical and Nuclear Chemistry Articles, 1992, Vol. 162, p355-, J.P. Shukla, Bis(2-ethylhexyl)sulfoxide as an Extractant for Americium (III) From Aqueous Nitrate Media

Talanta, 1992, Vol. 39, p493-, J.N. Mathur, Extraction of Actinides and Fission Products by Octyl(phenyl)-N,N-Diisobutylcarbomylmethylphosphine Oxide from Nitric Acid Media

Nuclear Technology, 1992, Vol. 100, p395-402, U.K. Mudali, Mixed RuO₂/TiO₂/PtO₂/-Coated Titanium Andoes for the Electrolytic Dissolution of Nuclear Fuels

Nuclear Science Journal, 1993, Vol. 30, p1-10, J.P. Shukla, Permeation of Plutonium (IV) Across Thin-Sheet Supported Liquid Membranes Using Dicyclohexano-18-Crown-6 as Mobile Carier

Journal of Nuclear Materials, 1993, Vol. 203, p73-82, U.K. Mudali, Corrosion Studies on Materials of Construction for Spent Nuclear Fuel Reprocessing Plant Equipment

Radiochemica Acta, 1993, Vol. 60, p109- , D.R. Prabhu, Extraction of Uranium (VI) and Plutonium (IV) With Unsymmetrical Monoamides

Radiochemica Acta, 1993, Vol. 62, p153-, P. Behera, Extraction of Mo(VI) and U(VI) by Alamine 310 and Its Mixtures From HCl Solution

Waste Management, 1993, Vol. 13, p317-25, J.N. Mathur, Partitiioning of Actinides from High-Level Waste Streams of PUREX Process Using Mixtures of CMPO and TBP in Dodecane

Journal of Radioanalytical and Nuclear Chemistry Articles, 1993, Vol. 175, p415-, J.N. Mathur, Solvent Extratced and Extraction Chromatographically Adsorbed Complexes of Bifunctional Extractants with F-Elements

Solvent Extraction and Ion Exchange, 1993, Vol. 11, p645-62, P.R. Vasudeva, The Effect of Diluent on Third Phase Formation in Thorium Nitrate - TBP System: Some Novel Empirical Correlations

Solvent Extraction and Ion Exchange, 1993, Vol. 11, p831-47, G.M. Nair, Tetra-Butyl-Malonamide and Tetra-Isobutyl-Malonamide as Extractants for Uranium (VI) and Plutonium (IV)

Journal of Nuclear Science and Technology, 1993, Vol. 30, p1198-200, J.N. Mathur, Extraction Chromatographic Separation and Recovery of Plutonium From Oxalate Supernatant Using CMPO

Bioresource Technology, 1994, Vol. 49, p179-86, T.R. Muraleedharan, Application Studies of Biosorption for Monazite Processing Industry Effluents

Separation Science and Technology, 1994, Vol. 29, p193-203, J.S. Gill, Transport of Samarium (III) and Uranium (VI) Across a Silicone-Supported Liquid Membrane Using Di(2-Ethylhexyl)phosphoric Acid and Tributyl Phosphate as Mobile Carriers

Journal of Radioanalytical and Nuclear Chemistry Articles, 1994, Vol. 182, p291-8, A. Palamalai, Final Purification of Uranium-233 Oxide Product From Reprocessing Treatment of Irradiated Thorium Rods

Journal of Radioanalytical and Nuclear Chemistry Articles, 1994, Vol. 182, p393-, G.M. Nair, Extraction of Uranium (VI) and Plutonium (IV) With Dihexylisobutyramide and Dihexylisobutyramide From Nitric Acid Medium

Solvent Extraction and Ion Exchange, 1994, Vol. 12, p633-50, P.B. Santhi, Synergistic Solvent Extraction of Trivalent Lanthanides and Actinide by Mixtures of 1-Phenyl-3-Methyl-4-Benzoyl-Pyrazalone-5 and Neutral Oxo-Donors

Solvent Extraction and Ion Exchange, 1994, Vol. 12, p727-44, A. Suresh, Extraction of U(VI), Pu(IV) and Th(IV) by Some Triakyl Phosphates

Solvent Extraction and Ion Exchange, 1994, Vol. 12, p745-63, J.N. Mathur, Separation and Recovery of Plutonium From Oxalate Supernatant Using CMPO

Separation Science and Technology, 1994, Vol. 29, p1001-1010, S. Prabhakar, Reverse Osmosis Separation of Radiocontaminants from Ammonium Diuranate Effluents

Journal of Nuclear Science and Technology, 1994, Vol. 31, p1066-72, J.P. Shukla, Influence of Gamma-Irradiation on Extraction and Cation-Transport of Uranium (VI) and Plutonium (IV) by Dicyclohexano-18-Crown-6

Solvent Extraction and Ion Exchange, 1994, Vol. 12, p1085-1101, K.N. Sabharwal, Extraction of Actinides by Bifunctional Phosphinic Acid Resin

Radiochimica Acta, 1995, Vol. 68, p69-73, V. Sagar, Synergic Extraction of Uranium (VI) from Different Aqueous Media Using HTTA and Neutral Donors

Nuclear Science Journal, 1995, Vol. 32, p92-100, J.P. Shukla, Extraction Characteristics of Uranium (VI), Plutonium (IV) and Some Fission Products with Radiolytically Degraded Bis(2-Ethylhexyl)Sulfoxide

Nuclear Technology, 1995, Vol. 114, p97-110, H.P. Nawada, Some Computations in Planning Reconstitution of a 500-MW (ELectric) Fast Breeder Reactor (Metallic) Fuel by Electrorefining

Waste Management, 1995, Vol. 15, p149-57, P.K. Sinha, Treatment of Radioactive Liquid Waste Containing Caesium by Indigenous Available Synthetic Zeolites: A Comparative Study

Nuclear Technology, 1995, Vol. 109, p216-25, J.N. Mathur, Extraction Chromatographic Separation of Minor Actinides from PUREX High-Level Wastes Using CMPO

Journal of Radioanalytical and Nuclear Chemistry Articles, 1995, Vol. 191, p291-303, J.P. Shukla, Reversed-Phase Partition Chromatographic Separation of Minor Actinides with Bis(2-Ethylhexyl)Sulfoxide from Acidic Nitrate PUREX Waste Solutions

Journal of Radioanalytical and Nuclear Chemistry Articles, 1995, Vol. 191, p323-30, G.M. Nair, Extraction of Uranium (VI) and Plutonium (IV) with Some High Molecular Weight Aliphatic Monoamides from Nitric Acid Medium

Solvent Extraction and Ion Exchange, 1995, Vol. 13, p301-12, A. Ramanujam, Extraction Chromatographic Separation of Promethium From High Active Waste Solutions of PUREX Origin

Solvent Extraction and Ion Exchange, 1995, Vol. 13, p415-30, A. Suresh, Studies on U-Th Separation Using Tri-sec-Butylphosphate

Solvent Extraction and Ion Exchange, 1995, Vol. 13, p561-74, K.N. Sabharwal, Extraction of Uranium by Macroporous Bifunctional Phosphinic Acid Resins

Journal of Nuclear Science and Technology, 1995, Vol. 32, p1127-37, H.P. Nawada, Thermochemical Modeling of Electrorefining Process for Reprocessing Spent Metallic Fuel

Nuclear Science Journal, 1996, Vol. 33, p1-7, G.R. Mahajan, Studies on the Extraction of Uranium (VI) and Plutonium (IV) by Dicyclohexylbutyramide and Dicyclohexylisobutyramide

Journal of Nuclear Materials, 1996, Vol. 228, p18-23, K. Ananthasivan, Reprocessing of Carbide Fuels: Conversion of Carbide to Nitride as a Head End Step

ESARDA Bulletin, 1996, Vol. 26, p22-3, P.R. Nair, A Simple, Rapid and Accurate Electrochemical Method for Uranium Determination in Dissolver Solution of Irradiated Fuel

Nuclear Science Journal, 1996, Vol. 33, p39-51, J.P. Shukla, Selective Solvent Extraction of Palladium (II) With Thiacrowns From Aqueous Chloride/Nitrate Reprocessing Waste Streams

Radiochimica Acta, 1996, Vol. 72, p93-6, N.S.B. Singh, Simultaneous Determination of U(IV) and Hydrazine

Journal of Nuclear Materials, 1996, Vol. 252, p119-24, G.P. Tiwari, Behavior of Inert Gas Bubbles Under Chemical Concentration Gradients

Journal of Pure and Applied Ultrasonics, 1996, Vol. 18, p125-30, B.K. Rout, Ultrasonic Studies on the Extracted Organic Phase of Uranium (VI) Using Tri-n-Butyl Phosphate (TBP)

Radiochimica Acta, 1996, Vol. 73, p185-90, K.V. Lohithakshan, Thermodynamics of Synergistic Extraction of Hexavalent Plutonium with HPMBP and Neutral Donors: Monodentate versus Bidentate

Radiochimica Acta, 1996, Vol. 73, p199-206, J.N. Mathur, Extraction of Np(IV), Pu(IV), and U(VI) with Amides, BEHSO and CMPO from Nitric Acid Medium

Journal of Radioanalytical and Nuclear Chemistry, Letters, 1996, Vol. 213, p225-32, D.R. Ghadse, Studies on the Recovery of Pu(IV) from Hydrochloric Acid - Oxalic Acid Solutions using an Anion Exchange Method

Journal of Radioanalytical and Nuclear Chemistry, Letters, 1996, Vol. 213, p419-29, J.N. Mathur, Recovery of Neptunium from Highly Radioactive Waste Solutions of PUREX Origin using CMPO

Journal of Radioanalytical and Nuclear Chemistry, Letters, 1996, Vol. 213, p431-9, K.M. Michael, Purification of Americium from Bulk Quantities of Plutonium Loading Effluent using Trilauraylamine

Journal of Radioanalytical and Nuclear Chemistry, Articles, 1996, Vol 203, p547-73, D.D. Sood, Chemistry of Nuclear Fuel Reprocessing: Current Status

Journal of Nuclear Science and Technology, 1996, Vol. 33, p1003-5, S. Kumar, Empirical Modelling of Pu(IV) Third Phase Formation in 30% TBP/n-Dodecane System

Separation Science and Technology, 1996, Vol. 21, p2045-63, J.N. Mathur, Recovery of Neptunium From Highly Radioactive Waste Solutions of PUREX Origin Using Tributyl Phosphate

Journal of Radioanalytical and Nuclear Chemistry, 1997, Vol. 219, p61-7, J.P. Shukla, Extraction of Uranium(VI), Plutonium(IV) and Some Fission Products by Tri-iso-Amyl Phosphate

Journal of Radioanalytical and Nuclear Chemistry, 1997, Vol. 221, p41-4, J.A. Daoud, Kinetic Studies on the Extraction of U(IV) in Kerosene from Nitrate Medium

Journal of Radioanalytical and Nuclear Chemistry, 1997, Vol. 223, p193-8, K. Venugopal Chetty, Effect of Mixed Solvent Media on the Sorption and Separation of Uranium and Plutonium on Macroporous Resins

Journal of Nuclear Science and Technology, 1997, Vol. 34, p1027-8, S. Kumar, A Numerical Model for Prediction of Boundary Acid Concentration for Prevention of Polymerization at Macro Pu Concentrations

Nuclear Engineering and Design, 1997, Vol. 178, p279-94, S. Narayanan, Non-Linear Dynamics of a Two Phase Flow System in an Evaporator: The Effects of (i) a Time Varying Pressure Drop (ii) an Axially Varying Heat Flux

Nuclear Engineering and Design, 1998, Vol. 179, p75-100, H.P. Nawada, Thermochemical Modelling of Electrotransport of Uranium and Plutonium in an Electrorefiner

Nuclear Technology, 1998, Vol. 123, p116-9, S. Kumar, Empirical Modelling of U(IV) Distribution in a Nitric Acid-Water-30%TBP/n-Dodecane Biphasic System in the Presence of U(VI), Pu(III), and Hydrazine Nitrate

Journal of Nuclear Materials, 1998, Vol. 252, p162-7, G.P. Tiwari, Reply to 'Comments on "Behavior of Inert Bubbles Under Chemical Concentration Gradients"

Transactions of the Indian Institute of Metallurgy, 1998, Vol. 51, p179-81, A.K. Singh, Flotation of Uranium Values Using Di(2-Ethyl-Hexyl)Phosphoric Acid

Radiochimica Acta, 1998, Vol 81, p189-93, S.A. Pai, Thermodynamics of Synergestic Extraction of Americium(III) with HTTA using DHDECMP(Bi-functional) and TBP(Mono-functional)

Journal of Radioanalytical and Nuclear Chemistry, 1998, Vol. 229, p203-6, R.M. Sawant, Study on the Extraction of U(IV) Relevant to PUREX Process

Journal of Nuclear Science and Technology, 1998, Vol. 35, p309-12, S. Kumar, Prediction of Densities of Mixed Organic Solutions Containing UO₂(NO₃)₂ and Nitric Acid

Nuclear Technology, 1998, Vol. 123, p335-40, S. Kumar, Prediction of Liquid Mixture Viscosity for Dry and Water-Saturated TBP/n-Dodecane Solutions

Journal of Nuclear Science and Technology, 1998, Vol. 35, p370-8, N.K. Pandey, Adsorption Kinetics and Breakthrough Behavior of Tri-n-Butyl Phosphate on Amberlite XAD-4 Resin

Journal of Nuclear Science and Technology, 1998, Vol. 35, p419-24, J.P. Shukla, Selective Permeation of Plutonium(IV) Through a Supported Liquid Membrane Containing Tri-iso-Amyl Phosphate as an Ionophore

Solvent Extraction and Ion Exchange, 1998, Vol. 16, p459-69, J.N. Mathur, Paraffin Wax as a Diluent for Extraction of Actinides and Lanthanides With TBP

Solvent Extraction and Ion Exchange, 1998, Vol. 16, p739-49, J.N. Mathur, Parafin Wax - TOPO, An Extractant for Actinides and Lanthanides

Separation Science and Technology, 1998, Vol. 23, p1401-8, T.G. Srinivasan, Effect of Uranium on Third Phase Formation in the Pu(IV)-HNO₃/TBP-Dodecane System

Separation Science and Technology, 1998, Vol. 33, p1877-87, R.R. Chitnis, Separation and Recovery of Uranium, Neptunium, and Plutonium From High Level Waste Using Tributyl Phosphate: Countercurrent Studies With Simulated Waste Solution

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p15-8, P.N. Pathak, Separation of uranium and Thorium using Tris(2-Ethylhexyl) Phosphate as Extraction

Radiochimica Acta, 1999, Vol. 85, p97-102, T.G. Srinivasan, Effect of Temperature on the Extraction of Plutonium(VI) by Tri n-Amyl Phosphate

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p99-103, S.P. Mohanty, Extraction of Uranium(VI) with a Binary Mixture of LIX-860 and Versatic-10

Radiochimica Acta, 1999, Vol. 85, p103-6, K.K. Gupta, Thermodynamics of Extraction of Uranium(VI) and Plutonium(IV) with some Long-chain Aliphatic Amides

Radiochimica Acta, 1999, Vol. 86, p129-34, P.N. Pathak, Solvent Extraction Studies on Th(IV), Pa(V), and U(VI) from Nitric Acid Medium using Di-2-EthylHexyl Isaobutramide (D2EHIBA)

Nuclear Technology, 1999, Vol. 127, p233-7, K. Venugopal, An Electrocatalyzed Process for Leaching of Plutonium from Active Gauntlets and Subsequent Separation by Solvent Extraction

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p375-7, A. Kumar, Distribution of Pu(VI) from Nitric Acid to tri-n-Butyl Phosphate Saturated with Uranium (VI)

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p631-5, P.M. Mapara, Extraction of Uranium and Plutonium from Oxalate Bearing Solutions using Phosphonic Acid: Solvent Extraction, Extraction Chromatography and Infrared Studies

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p721-6, R.R. Chitnis, Recovery of Actinides Extracted by TRUEX Solvent fromHigh Level Waste using Complexing Agents. I. Batch Studies

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p727-30, R.R. Chitnis, Recovery of Actinides Extracted by TRUEX Solvent fromHigh Level Waste using Complexing Agents. II. Counter-current Studies

Journal of Radioanalytical and Nuclear Chemistry, 1999, Vol. 240, p981-5, I.C. Pius, Studies on the Separation of Pu(IV) on Alumina Microspheres from Nitric Acid - Oxalic Acid Solutions

Separation Science and Technology, 1999, Vol. 34, p1717-28, A. Ramanujam, Partitioning of Actinides From High Level Waste of PUREX Origin Using Octylphenyl-N-N'-Diisobutylcarbomoylmethyl Phosphine Oxide (CMPO) Based Supported Liquid Membrane

Separation Science and Technology, 1999, Vol. 34, p2601-14, P.N. Pathak, Separation Studies of Uranium and Thorium Using Di-2-Ethylhexyl Isobutyramide (D2EHIBA)

Separation Science and Technology, 1999, Vol. 34, p2887-2903, S.C. Tripathi, Effect of Solvent Recycling on Radiolytic Degradation of 30% Tributyl Phosphate-n-Dodecane-HNO₃ System

Nuclear Technology, 2000, Vol. 129, p279-83, S. Kumar, Salt Effect Model for aqueous Solubility of TBP in a 5 to 100% TBP/n-Dodecane-Nitric Acid-Water Biphasic System at 298.2 K

Solvent Extraction and Ion Exchange, 2000, Vol. 18, p307-17, V. Sagar, Extraction of Plutonium (III) by TBP in Presence of Uranium

Journal of Radioanalytical and Nuclear Chemistry, 2000, Vol. 243, p697-700, M.M. Charyulu, Concentration with Selective Acid Removal from Americium Solutions using Ion Exchange Membranes

Separation Science and Technology, 2000, Vol. 35, p1603-17, K.K. Gupta, N,N-Dihexyl Hexanamide: A Promising Extractant for Nuclear Fuel Reprocessing