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Nuclear Fuel Fabrication

Materials Science Forum Volumes 48 - 49

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• p1 The Growth and Development of Plutonium Fuels Technology in India   [ 2 M ]
  Authors: P.R. Roy
• p9 Fabrication of Fuel for Water Reactors   [ 3 M ]
  Authors: G.V.S.R.K. Somayajulu, N. Swaminathan, R. Rajendran, K. Balaramamoorthy
• p21 Development of Cladding and Structural Materials for Thermal and Fast Reactor Programme in India   [ 8 M ]
  Authors: C.V. Sundaram, P. Rodriguez, S.L. Mannan, S. Venkadesan
• p49 Choice of Fuel Material for India's Fast Reactor Programme   [ 4 M ]
  Authors: S.R. Paranjpe
• p63 Super Phenix Core Fabrication   [ 25 M ]
  Authors: R. Vandevoir
• p73 Main Options for Super-Phenix Core Assemblies Design   [ 55 M ]
  Authors: F. Rouches, J.C. Nervi
• p95 Design Aspects of Metallic Fuel for Research Reactors and Ceramic Fuel for Boiling Water Reactors   [ 35 M ]
  Authors: S.K. Metha, K. Anantharaman, S.M. Chaudhary, K.R. Srinivasan
• p109 Design Aspects of PHWR for Improved Performance   [ 5 M ]
  Authors: M. Das
• p125 Thorium Utilisation in Indian Power Programme   [ 35 M ]
  Authors: Kamala Balakrishnan, C. Ganguly
• p139 Manufacture of the First Charge for the Super-Phenix Reactor   [ 4 M ]
  Authors: J. Pajot, M. Beche, M.J. Heyraud
• p153 Fabrication of (U, Pu)C and (U, Pu)N Fuels for FBTR and PFBR   [ 38 M ]
  Authors: C. Ganguly, P.V. Hegde, G.C. Jain, U. Basak
• p175 Alternative Fuels for the French Fast Breeder Reactors Programme   [ 3 M ]
  Authors: H. Bailly, H. Bernard, B. Mansard
• p185 Modifications in the "Powder-Pellet" Route for Higher Recovery and Reduced Fuel Fabrication Cost of UO₂/MOX Fuel   [ 40 M ]
  Authors: S. Majumdar, M.R. Nair, R. Ramachandran, H.S. Kamath
• p201 Zirconium Alloys as Cladding and Structural Materials for Water Cooled Reactors   [ 50 M ]
  Authors: M.K. Asundi, S. Banerjee
• p221 MOX Fuel Plans in LWRs   [ 3 M ]
  Authors: G. Lebastard