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Alternative Fuels for the French Fast Breeder Reactors Programme
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Modifications in the "Powder-Pellet" Route for Higher Recovery and Reduced Fuel Fabrication Cost of UO₂/MOX Fuel
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Zirconium Alloys as Cladding and Structural Materials for Water Cooled Reactors
p.201

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MOX Fuel Fabrication Experience and MOX Plant
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Experience in BARC on the Preparation of Gel Microspheres of Uranium, Thorium and Plutonium Fuels
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HomeMaterials Science ForumMaterials Science Forum Vols. 48-49Zirconium Alloys as Cladding and Structural...

Zirconium Alloys as Cladding and Structural Materials for Water Cooled Reactors

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Nuclear Fuel Fabrication

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Periodical:

Materials Science Forum (Volumes 48-49)

Pages:

201-220

DOI:

https://doi.org/10.4028/www.scientific.net/MSF.48-49.201

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Online since:

January 1989

Authors:

M.K. Asundi, S. Banerjee

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© 1989 Trans Tech Publications Ltd. All Rights Reserved

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