Materials Science and Technology, Nuclear Materials
Brian R. T. Frost
Wiley, Apr 28, 1994 - Technology & Engineering - 578 pages
The first of two volumes in this series to deal with the information required for the use of materials in the nuclear power industry. The two volumes together contain the most comprehensive collection of information ever published in nuclear materials.
Contents: Walters/Hofman: Metallic Fast Reactor Fuels. Snelgrove/Hofman: Dispersion Fuels. Strain/Lambert: Oxide Fuels. Blank: Non-Oxide Ceramic Nuclear Fuels. Kelly: Nuclear Reactor Moderator Materials. Garner: Cladding.
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Nuclear Reactor Moderator Materials
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alloys annealed atoms austenitic behavior burnup carbide carbide and nitride carbide fuel carbon ceramic changes cladding coefficient Conf coolant core curve decrease densification density diffusion dislocation dispersion fuel dose EBR-II effect energy etal fabrication Fast Breeder Reactor fast reactor Figure fission gas fission products fission rate flux fuel element fuel meat fuel particles fuel pins fuel plates fuel rod fuel-cladding Garner gas release grain boundary graphite He-bonded heat high burnup IAEA in-pile increase irradiation irradiation temperature material matrix Matzke mechanism ments metallic fuel microstructural MX-type fuels neutron nitride nitride fuels Nucl operation oxide oxygen pellet perature phase plutonium pore porosity Proc properties radial reac reaction Reactor Fuel shown in Fig sintering solid stainless steel stoichiometric strains stress structure surface swelling rate Table tempera thermal conductivity thermal expansion tion ture uranium vacancy void volume zone