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Nuclear graphite tensile

T. D. Burchell and J. P. Strizak. Modelling the Tensile Strength of H-451 Nuclear Graphite. In Proc. 21 Biennial Conf on Carbon, Buffalo NY, USA.. Pub. American Carbon Society, 1993, pp. 687 688. [Pg.532]

Strizak, J.P. The effect of volume on the tensile strength of several nuclear-grade graphites. In Proceeding of the IAEA Specialists meeting on the Status of Graphite Development for Gas Cooled Reactors, IAEA-TECHDOC-690, IAEA, Vienna, 1993, pp. 233 240. [Pg.479]

J. P. Strizak, The Effect of Volume on the Tensile Strength of Several Nuclear Grade Graphites, Proceedings of a Specialists Meeting on The Status of Graphite Development for Gas Cooled Reactors. Tokai-mura, Japan, 1991... [Pg.534]

See other pages where Nuclear graphite tensile is mentioned: [Pg.490]    [Pg.514]    [Pg.511]    [Pg.535]    [Pg.490]    [Pg.514]    [Pg.479]    [Pg.515]    [Pg.486]    [Pg.507]    [Pg.739]    [Pg.486]    [Pg.621]    [Pg.420]   
See also in sourсe #XX -- [ Pg.512 , Pg.513 , Pg.514 ]



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Nuclear graphite

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