Documents:

AEET/ROD/3,Corrosion and Deposition Problems in Canada India Reactor Fuel Rod Cladding, V.S. Rao,1962

AEET/ROD/5,Water Chemistry in Canada India Reactors,V.S. Rao,1962

AEET-252,Fuel Cycles in PHWR and CANDU Type Reactors,B.P. Rastogi,1966

AEET-269, Utilization of Thorium in Power Reactors,B.P. Rastogi, 1966

BARC/I-61, Literature Survey on Plutonium Bearing Carbide Fuels. Properties and Potentials of Uranium-Plutonium Carbides as Fast Reactor Fuels - A Review,B.D. Zope,1970

BARC-513,Kinetics of Release of Xenon from Sintered (ThO₂-0.1 Percent UO₂) Pellets,M.D. Karkhanavala,1971

BARC-538,Post-Irradiation Thermal Release Study of Fission Gases from Fuel Pellets,O.P. Chawla,1971

BARC-666, Chemistry of Radiation Problems in Reactors,D.G. Vartak,1973

BARC-918, Fabrication and Post-Irradiation Examination of a Zircaloy-2 Clad UO₂-1.5% PuO₂ Fuel Pin Irradiated in PWL, Cirus, D.N. Shah, 1977

BARC-984, Metallographic Examination of Irradiated Nuclear Fuel Elements at Radiometallurgy Hot Cell Facility, D.N. Sah,1978

INIS-mf-4826,Reactivity Prediction of Uniform PuO₂-UO₂ Fueled Lattices and Pu(NO₃)₄ Solutions in Light Water, P. Mohankrishnan, 1978

INIS-mf-4835,Design Criteria for Confidence in the Manufacture of BWR Fuel Rods,K. Anantharaman,1978

BARC-1014,Post-Irradiation Examination of Fuel Elements of TARAPUR Atomic Power Station,J.K. Bahl,1979

BARC-1078,Indigenisation of Lubriplate 630-2 and Development of Servo-Nuclease-2 Grease for the Fuelling Machine of Pressurized Heavy Water Reactors ,S.B. Srivastava,1980

BARC-1092,Chemistry and Material Compatibility Problems in Dissociating Gas-Cooled Fast Reactors, P.C. Das,1981

BARC-1182,Development of UO₂-30 Wt. Percent PuO₂ Fuel for FBTR, S. Majumdar,1983

BARC-1185 ,Hot Vacuum Outgassing to Ensure Low Hydrogen Content in MOX Fuel Pellets for Thermal Reactors ,S. Majumdar,1983

BARC-1193,Penetrating Radiation as a Tool for the Quality Evaluation of Nuclear Fuels,J.P. Ghosh,1983

BARC-1250,Computerized Automatic Pellet Inspection Unit for FBTR Fuel ,No Author,1984

BARC-1421,Advanced Methods for Fabrication of PHWR and LMFBR Fuels, C. Ganguly,1988

BARC-1472,Evaluation of Bonding in Kamini Plate Type Fuel Elements Using Ultrasonic Immersion Testing and Metallography, S. Muralidhar,1989

BARC-1501,Thermodynamic Analysis of Advanced Fuels for Fast Breeder Reactors,D. Srivastava,1990

Conference Papers:

Nuclear Power and Its Fuel Cycle, 1977, p271-84, G.R. Udas, Uranium and Thorium Resources and Development of techniques and Equipment for Their Prospection

Nuclear Power and Its Fuel Cycle, 1977, p517-26, R.N. Kondal, Integrated Planning for a Fuel Industry, with Emphasis on the Minimum Size Appropriate for Fabricating One’s Own Fuel

Proceedings of the Conference on Characterization and Quality Control of Nuclear Fuel, 1978, R.N. Kondal Technological Aspects of UO₂ Fuels. Characterization and Quality Control. Indian Experience

IAEA International Symposium on Water Reactor Fuel Element Fabrication with Special Emphasis on its Effect of Fuel Performance, 1978, J.K. Bahl

Indian Experience in Performance of Light Water Reactor Fuel Elements Proc. of Afro-Asian Conference On Welding and Metals Technology, 1978, J.K. Ghosh, Inspection of End Closure Welds of Fast Reactor Fuel Elements

Soudage Fusion Faiscaeau Electrons 1978, 2^nd, p245-52, G.L. Prasad, Electron Beam Welding in the Fabrication of Plate-Type Fuel Elements

Proc. Symp. Sintering Sintered Prod., 1979, p335-42, M. Das, Characterization of Sintered Uranium Dioxide Pellets Relevant to Fuel Design and Performance

Proc. Symp. Sintering Sintered Prod., 1979, p357-73, D.D. Sood, Preparation of Ceramic Nuclear Fuels: Sol-Gel Process

Proc. Symp. Sintering Sintered Prod., 1979, p401-21, P. Balakrishna, Fabrication of Burnable Poison Fuel Pellets for TAPS - Plant Experience

Proc. Symp. Sintering Sintered Prod., 1979, p423-41, C. Ganguly, Powder Metallurgy in the Fabrication of (Uranium-Plutonium) Carbide, (Uranium-Plutonium) Nitride, and (Uranium-Plutonium) Carbonitride Fuels for Fast Breeder Reactors

Proc. Symp. Sintering Sintered Prod., 1979, p443-54, S. Majumdar, Low Density Uranium Dioxide and (Uranium-Plutonium) Dioxide Pellet Fabrication

Fast Reactor Fuel Cycles, Proc. Int. Conf., 1981, p181-8, C. Ganguly, Fabrication of Advanced LMFBR Fuels at BARC Fast Reactor Fuel Cycles, Proc. Int. Conf., 1981, p233-6, B. Singh, Optimization of Fuel Pin Diameter for Oxide and Carbide Fuels for a Medium Sized Fast Breeder Reactor

Fast Reactor Fuel Cycles, Proc. Int. Conf., 1981, p243-6, S.M. Lee, Fuel Management in a Medium Sized Fast Breeder Reactor Sintered Metal-Ceramic Composites.

Proceedings of the Third International School on Sintered materials, New Delhi, India, 1983, P.R. Roy, Dispersion Type Composites for Nuclear Reactors

Improved Util. Water React. Fuel Spec. Emphasis Ext. Burnups Plutonium Recycle Proc. Spec. Meeting, 1984, p227-40, H.S. Kamath, Some Aspects of Plutonium Recycling in Thermal Reactors

Proceedings of the Seminar on Remote Handling Equipment for Nuclear Fuel Cycle Facilities, 1984, p119-34, P.R. Roy, Remotisation in the Production of Fast Reactor Fuels in India

Proc. of DAE Symp. on Radiochemistry and Radiation Chemistry, 1985, G.C. Jain, Process Control Analysis in Mixed Carbide Fuel Pellets

Improvements in Water Reactor Fuel Technology and Utilization, Stockholm, Sweden, 1986, S.A. Bhardwaj, Fuel Design Evolution in Indian PHWR’s

Improvements in Water Reactor Fuel Technology and Utilization, Stockholm, Sweden, 1986, p557, H.S. Kamath, Studies of New Fabrication Techniques for UO₂ and Mixed Oxide Fuel for Improved Performance and Economics

Improvements in Water Reactor Fuel Technology and Utilization, Stockholm, Sweden, 1986, p493-503, G.V.S.R.K. Somayajulu, PHWR/BWR Fuel Manufacturing Experience in India

International Conference on CANDU Fuel, 1986, p39-51, G.V.S.R.K. Somayajulu, PHWR Fuel Fabrication - Indian Experience

Canadian Nuclear Society 8^th Annual Conference 1987 Proceedings, 1987, p236-40, J.E. Kowalski, Experimental Investigation of the Refill Behavior in a CANDU-Type Header/Feeder System

Nuclear Fuel Fabrication, Proceedings of a Symposium on Nuclear Fuel Fabrication, NUFFAB’88, Held at the Bhabba Atomic Research Centre, Bombay, 1988, C. Ganguly (Editor)

Session One: Overview of Fuels

Session Six: Engineering Development and Safety in Fuel Fabrication

Session Seven: Research Reactor Fuel Fabrication

Session Eight: Quality Control of Nuclear Fuels

Session Nine: Performance and P.I.E. of Fuels

Emerging Nuclear Energy Systems, 1989, p91-4, M. Srinivasan, The Emerging Option of Fusion Reactors for the Early Exploitation of Thorium in the Indian Context

Winter Meeting of the American Nuclear Society, 1989, Vol.60, p663-4, M.P. Antony, A New Radiochemical Hot Cell Facility at Kalpakkam for the Study of Advanced Fuels

National Conference on Nuclear Science and Technology in India - Past, Present and Future, 1989, V.N. Vaidya, Sol Gel Routes for Fuel Fabrication

National Conference on Nuclear Science and Technology in India, Past. Present and Future, 1989, S.G. Marathe, Chemical Aspects of Quality Control of the Plutonium Based Fuel Development Programme

Proceedings of the Second International Conference on Candu Fuel, 1989, C. Ganguly, Sol Gel Microspheres Pelletisation of UO₂ and UO₂-PuO₂ Pellets of PHWR Fuel Specification Using Internal Gelation Process

Proceedings of the Second International Conference on Candu Fuel, 1989, C. Ganguly, ThO₂ Based Fuels for PHWR’s: Fabrication, Characterization and Test Irradiation

Thorium Util. Proc. Indo-Japanese Semin., 1990, p77-85, C. Ganguly, Development of Thorium Based Fuels for Water-Cooled Reactors

Thorium Util. Proc. Indo-Japanese Semin., 1990, p99-104, R. Vijayaraghavan, Production and Fabrication of Thorium Fuels at BARC

Thorium Util. Proc. Indo-Japanese Semin., 1990, p132-5, K. Anantharaman, Loop Experiments with Thoria Based Fuels

Thorium Util. Proc. Indo-Japanese Semin., 1990, p137-47, V.S. Keni, Extraction and Refining of Thorium

Fourth International Conference on Characterization and Quality Control of Nuclear Fuels, 1990, p234-41, C. Ganguly, Preparation, Characterization and Out-of-Pile Property Evaluation of (U,Pu)N Fuel Pellets

Proceedings of the National Symposium On Computer Applications in Power Plants, 1992, p19-24, K. Jayarajan, Robots in Nuclear Fuel Fabrication

Third International Conference on CANDU Fuel, 1992, p1/18-28, K. Balaramoorthy, Self-Reliance in PHWR Fuel Production

Third International Conference on CANDU Fuel, 1992, p8/1-14, C. Ganguly, SGMP-LTS Process for Fabrication of High Density UO₂ and (U,Pu)O₂ Fuel Pellets

Third International Conference on CANDU Fuel, 1992, p8/35-44, R.N.R. Jaya, Resistance Welding as Applied to Fuel Fabrication for PHWR’s - An Indian Experience

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, U.C. Gupta, Development of Fluidized-Bed Furnace for Thermal Treatment of Ammonium Uranyl Carbonate

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, P. Balakrishna, Some Aspects of UO₂ Powder Production

1997 Winter Meeting. American Nuclear Society, 1997, P.D. Krishani, Method of Calculating the Effect of Heterogenous Fuel Composition on a Fuel Bundle Ramp

Proceedings of the International Topical Meeting on Advanced Reactor Safety, 1997, Orlando, FL, A.N. Kumar, MOX Fuel Designs to Increase Void Reactivity in Indian PHWR’s

Top Fuel 97, Proceddings of the International Topical Meeting on Nuclear Fuel, 1997, Manchester, UK, P. Balakrishna, Agglomerate-free Fine UO₂ Powders

5^th International Union of Materials Research Societies International Conference, Bagalore, India, 1998, P. Rodriquez, Mixed Plutonium-Uranium Carbide Fuel in Fast Breeder Test Reactor

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 Samples and Total Uranium in Solution

Trans. Power Metallurgy Assoc. India, 1978, Vol. 5, p28-36, C. Ganguly, Preparation of Carbide Powders for Nuclear Reactor Fuels

Transactions of the Powder Metallurgical Association of India, 1979, Vol. 6, p64-, R. Ramachandran

Influence of Some Production Parameters on Characteristics of Sintered Oxide Fuel Pellets for Fast Reactors

Journal of Nuclear Materials, 1981, Vol. 100, p227-49, P. Rodriquez, Nuclear and Material Aspects of the Thorium Fuel Cycle

Transactions of the Powder Metallurgy Association of India, 1982, Vol. 9, p18-23, R. Ramachandran, Surface Defects in Nuclear Fuel Pellets

Journal of Nuclear Materials, 1982, Vol. 106, p81-6, J. B. Patro, UO₂ Fuels - Qualitative Approach for Characterization

Nuclear Tracks and Radiation Measurements, 1982, Vol. 6, p109-13, N.K. Chaudhuri, Analysis of Uranium and Plutonium in Binary Mixtures using the Technique of Track Registration from Solutions

Trans. Powder Metallurgy Assoc. India, 1983, Vol. 10, p8-14, H.S. Kamath, Carbon Dioxide - A Low Temperature Sintering Atmosphere for Thermal Reactor Oxide Fuels

Trans. Powder Metallurgy Assoc. India, 1983, Vol. 10, p15-18, S. Majumdar, Choice of Proper Powder Lubricant for the Production of Ceramic Nuclear Fuel Pellets

Trans. Powder Metallurgy Assoc. India, 1983, Vol. 10, p52-8, P.R. Roy, Pellet-Impregnation Technique for Preparation of Thorium Dioxide-Uranium Dioxide Fuel

NDT International, 1983, Vol. 16, p275-6, J.K. Ghosh, Monitoring Plutonium Enrichment in Mixed-Oxide Fuel Pellets Inside Sealed Nuclear Fuel Pins by Neutron Radiography

Material Science Monographs, 1984, Vol. 25, p159-79, P.R. Roy, Dispersion Type Composites for Nuclear Reactors

Trans. Powder Metallurgy Assoc. India, 1985, Vol. 12, p61-8, H.S. Kamath, Development of Higher Grain Size Uranium (IV) Oxide and MOX Fuels

Nuclear Technology, 1986, Vol. 73, p84-95, C. Ganguly, Sol-Gel Microsphere Pellitization Process for Fabrication of High-Density ThO₂/-2%UO₂ Fuel for Advanced Pressurized Heavy Water Reactors

Tool Alloy Steels, 1986, Vol. 20, p97-106, P.R. Roy, Stainless Steels for Nuclear Industries

Tool Alloy Steels, 1986, Vol. 20, p113-16, R. Prabhudoss, Alloy Steel for Valve Components

Trans. Powder Metallurgy Assoc. India, 1986, Vol. 13, p105-11, U. Basak, Fabrication of Thorium Dioxide-4% Uranium Dioxide and Thorium Dioxide-4% Plutonium Dioxide Fuel Pellets for Pressurized Heavy Water Reactors

Nuclear Technology, 1986, Vol. 72, p59-69, C. Ganguly, Development and Fabrication of 70% PuC-30% UC Fuel for the Fast Breeder Test Reactor in India

Nuclear Technology, 1986, Vol. 73, p84-95, C. Ganguly, Sol-Gel Microsphere Pellitization Process for the Fabrication of High-Density Thorium Dioxide-Uranium Dioxide Fuel for Advanced Pressurized Heavy Water Reactors

Material Science Monographs, 1987, Vol. 38C, p2887-96, C. Ganguly, Advanced Fuels and Advanced Fuel Fabrication Methods in India

Journal of Radioanalytical and Nuclear Chemistry, 1988, Vol. 121, p29-43, A.U. Bhanu, Assay of Uranium in Scrap and Waste Produced at Natural Uranium Metal Production and Fuel Fabrication Plants

Journal of Nuclear Material, 1988, Vol. 152, p169-77, E. Zimmer, SGMP - An Advanced Method for Fabrication of Uranium Dioxide and MOX Fuel Pellets

Journal of Nuclear Material, 1988, Vol. 153, p177-88, C. Ganguly, The Role of Process Control and Inspection Steps in the Quality Assurance of SS316 Clad Mixed Plutonium-Uranium Carbide Fuel Pins for FBTR

Material Science Forum, 1988, Vol. 34, p845-9, C. Ganguly, Sol-Gel Microsphere Pellitization of Ceramic Nuclear Fuels

Trans. Indian Ceramic Society, 1988, Vol. 47, p16-71, C. Ganguly, Advanced Methods for the Fabrication of Mixed Uranium-Plutonium Oxide, Monocarbide, and Mononitride Fuels for Fast Breeder Reactors

Material Science Forum, 1989, Vol. 48, p1-7, P.R. Roy, The Growth and Development of Plutonium Fuels Technology in India

Material Science Forum, 1989, Vol. 48, p9-19, G.V. Somayajulu, Fabrication of Fuel for Water Reactors

Sadhana, 1989, Vol. 14, p21-57, C.V. Sundaram, Nuclear Fuels and Development of Nuclear Fuel Elements

Material Science Forum, 1989, Vol. 48, p95-108, K.S. Mehta, Design Aspects of Metallic Fuel for Research Reactors and Ceramic Fuel for Boiling Water Reactors

Material Science Forum, 1989, Vol. 48, p153-73, C. Ganguly, Fabrication of Mixed Uranium-Plutonium Monocarbide and Mononitride Fuels for FBTR and PFBR

Material Science Forum, 1989, Vol. 48, p185-200, S. Majumdar, Modifications in the "Powder-Pellet" Route for Higher Recovery and Reduced Fuel Fabrication Cost of Uranium Dioxide/Mixed Oxide (MOX) Fuel

Material Science Forum, 1989, Vol. 48, p231-48, D.S.C. Purushotham, MOX Fuel Fabrication Experience and MOX Plant

Material Science Forum, 1989, Vol. 48, p245-55, D.D. Sood, Experience in BARC on the Preparation of Gel Microspheres of Uranium, Thorium, and Plutonium Fuels

Journal of the Institution of Electronics and Telecommunications Engineers, 1989, Vol. 35, p251-6, M.S. Ramakumar, Flexible Manufacturing Systems and Their Relevance in Nuclear Fuel Fabrication in India

Material Science Forum, 1989, Vol. 48, p257-68, G.L. Goswami, Encapsulation of Plutonium-Based Fuel Pins

Material Science Forum, 1989, Vol. 48, p329-46, R. Vijayaraghavan, Experiences in the Fabrication of Aluminum-Clad Metallic Uranium Fuel

Key Engineering Materials, 1989, Vol. 29, p651-68, P.R. Roy, Recent Developments in P/M Techniques Used in Fabrication of Plutonium Bearing Ceramic Nuclear Fuels

Trans. Powder Metallurgy Assoc. India, 1990, Vol. 17, p1-6, C.R. P. Setty, Fabrication of Sintering Furnace for Uranium Oxide Fuel - NFC Experience

Trans. Powder Metallurgy Assoc. India, 1990, Vol. 17, p19-24, C. Ganguly, Microstructure Improvement of Uranium Dioxide and Uranium Dioxide-4% Plutonium Dioxide Fuel Pellets by Sol-Gel Microsphere Pelletization Method

Trans. Powder Metallurgy Assoc. India, 1990, Vol. 17, p43-8, C. Ganguly, Sol-Gel Microsphere-Pellitization Process for Preparation of Uranium Monocarbide and Uranium Mononitride Pellets

Trans. Powder Metallurgy Asoc. India, 1990, Vol. 17, p55-61, M. Das, Uranium Dioxide Pellets for PHWR’s - Design Quality Requirements and Manufacture

Journal of Nuclear Materials, 1990, Vol. 174, p76-9, P. Das, Further Interpretations of Sintering Data in Zirconia-Urania Mixed Oxide Powder Compacts

Met. Material Processes, 1990, Vol. 1, p253-74, C. Ganguly, Sol-Gel Microsphere-Pellitisation Process for Fabrication of Conventional and Advanced Ceramic Nuclear Fuels

Journal of Nuclear Materials, 1990, Vol. 173, p255-60, B. Venkataramani, A Novel Surface Treatment to Improve the Quality of Sintered UO₂ Pellets

Journal of Nuclear Material, 1991, Vol. 178, p234-41, C. Ganguly, Preparation, Characterization and Out-of-Pile Property Evaluation of Uranium-Plutonium Nitride Fuel Pellets

Indian Journal of Technology, 1990, Vol 28, p296-319, C. Ganguly, Alloy and Ceramic Nuclear Fuels Development and Fabrication at Bhabha Atomic Research Center

Diffusion and Defect Data - Solid State Data, 1990, Vol. B8-9, p415-32, P.R. Roy, Sintering Technology in the Manufacture of Nuclear Fuels

Diffusion and Defect Data - Solid State Data, 1990, Vol. B8-9, p433-44, C. Ganguly, "Additives" in Sintering Advanced Nuclear Fuel Pellets

Material Science Monographs, 1991, Vol. 66D, p2977-94, C. Ganguly, Advances in Fabrication Routes of Ceramic Nuclear Fuels

Material Science Monographs, 1991, Vol. 66D, p3003-16, P. Balakrishnam, Sintering Uranium Dioxide-Gadolinium Oxide

Key Engineering Material, 1991, Vol. 56, p435-69, C. Ganguly, Ceramic Nuclear Fuels Development at BARC - Recent Activities

Nuclear Technology, 1991, Vol. 96, p72-83, C. Ganguly, Fabrication Experience of Aluminum-Uranium-233 and Aluminum-Plutonium Plate Fuel for the PURNIMA III and KAMINI Research Reactors

Nuclear Technology, 1991, Vol. 96, p169-77, N. Kumar, Studies of the Preparation of Thoria and Thoria-Urania Microspheres Using an Internal Gelation Process

Journal of Nuclear Materials, 1991, Vol. 178, p179-83, C. Ganguly, Fabrication of High Density UO₂ Fuel Pellets Involving Sol-Gel Microsphere Pelletisation and Low Temperature Sintering

Journal of Nuclear Materials, 1991, Vol. 178, p234-41, C. Ganguly, Preparation, Characterization and Out-of-Pile Property Evaluation of (U,Pu)N Fuel Pellets, Diffus. Defect. Data, 1992, Part B, Vol. 25, p277-84, C. Ganguly, Sintering Behavior of Ceramic Nuclear Fuel Pellets Prepared from Sol-Gel Microspheres

Journal of Nuclear Materials, 1994, Vol. 210, p107-14, S.K. Mukerjee, Kinetics and Mechanism of UO₂ + C Reaction for UC/UC₂ Preparation

Nuclear Technology, 1994, Vol. 105, p346-54, C. Ganguly, Fabrication of (Pu_0.55U_0.45)C Fuel Pellets for the Second Core of the Fast Breeder Test Reactor in India

Nuclear Instruments and Methods in Physics Research, Section A, 1994, Vol. A337, p594-7, P.C. Kalsi, Assay of Uranium in U-Bearing Waste Produced at Natural Uranium Metal Fuel Fabrication Plants by Gamma-Ray Spectroscopy

Journal of Nuclear Materials, 1996, Vol. 230, p140-7, S. Suranarayana, Fabrication of UO₂ Pellets by Gel Pelletization Technique Without Addition of Carbon as Pore Former

Nuclear Technology, 1997, Vol. 117, p299-305, M.P. Anthony, Studies on the Restructuring of Fast Breeder Reactor Fuel by Out-of-Pile Simulation

Journal of Sol-Gel Science and Technology, 1997, Vol. 9, p285-94, C. Ganguly, Sol-Gel Microsphere Pelletisation Process for Fabrication of (U,Pu)O₂, (U,Pu)C, and (U,Pu)N Fuel Pellets for the Prototype Fast Breeder Reactor in India

Journal of Nuclear Materials, 1999, Vol. 264, p10-19, T.R.G. Kutty, Densification Behavior of UO₂-50%PuO₂ Pellets by Dilatometry

Bulletin of Materials Science, 1999, Vol. 22, p215-20, P. Rodriquez, Mixed Plutonium-Uranium Carbide Fuel in Fast Breeder Test Reactor

Nuclear Technology, 1999, Vol. 127, p375-81, P. Balakrishna, Uranium Dioxide Powder Preparation, Pressing and Sintering for Optimum Yield

Journal of Nuclear Materials, 1999, Vol. 264, p10-19, T.R.G. Kutty, Densification Behavior of UO₂-50%PuO₂ Pellets by Dilatometry