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Graphite moderator lifecycle behaviour.
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The design of gas-cooled graphite-moderated reactors.
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HTGR [High Temperature Gas Cooled and Graphite Moderated Reactors] technologies: proceedings.
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Uranium and graphite.
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Nuclear graphite.
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Nuclear graphite.
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Sodium graphite reactors
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Carbon and graphite handbook.
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Nuclear criticality safety based on limiting and controlling moderators.
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Gas transport in Graphitic Materials.
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Nondestructive testing of nuclear graphite.
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Study of the effective temperatures of two neutron moderating materials: Ethane and triphenylmethane
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Structure of sodium chloride cleavage surfaces etched in vacuum at moderate temperature.
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Surface area and porosity of graphitic materials.
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Calculation and measurement of the modular temperature coefficient of reactivity for water moderated power 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 status of graphite development for gas cooled reactors.
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Against behaviouralism: a critique of behavioural science
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Moderation of neutrons by elastic collisions in a heavy monatomic gas, allowing for thermal agitation
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The effect of pile irradiation on the linear dimensions of AGXP graphite.
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Interactions of hydrogen with graphite at low pressure and elevated temperature.
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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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Computational study on the buckling-reactivity conversion factor in light water moderated UO2 core.
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Author: Specialists meeting on graphite moderator lifecycle technologies Bath,GB
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Graphite moderator lifecycle behaviour.
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