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Nuclear graphite.
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Nuclear graphite.
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Nondestructive testing of nuclear graphite.
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Uranium and graphite.
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Sodium graphite reactors
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Carbon and graphite handbook.
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Gas transport in Graphitic Materials.
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Graphite moderator lifecycle behaviour.
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Surface area and porosity of graphitic materials.
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The status of graphite development for gas cooled reactors.
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The biaxial strength and fracture criteria for HTGR graphites.
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Determination of chlorine in graphite by combustion-ion chromatography.
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The design of gas-cooled graphite-moderated reactors.
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Mean Free Path of Nuclear Interaction for High-energy Particles in Graphite
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Interactions of hydrogen with graphite at low pressure and elevated temperature.
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The effect of pile irradiation on the linear dimensions of AGXP graphite.
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The Neutron Spectrum from a Fission Source in Graphite
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ZnO Nanowires on Graphite with Improved UV Photoluminescence
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Irradiation damage in graphite due to fast neutrons in fission and fusion systems.
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Influence of graphite discs, chamfers, and plenums on temperature distributions in high burnup fuel.
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The diffusion of Ag in the graphitic matrices A3-3 and A3-27.
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HTGR [High Temperature Gas Cooled and Graphite Moderated Reactors] technologies: proceedings.
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Flowsheet for the reprocessing of type 2, RA-1 fuel elements containig graphite
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Effective hydrogen production by hydrolysis of Mg wastes reprocessed by mechanical milling with iron and graphite
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Strength and elastic properties of some graphites, carbon/carbon and SiC/SiC composite materials.
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Author: Organisation européenne de coopération economique, Dragon project symposium Bournemouth,GB
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