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- W199409223 abstract "Any reactor design requires an exact knowledge about the capture cross section of passive'' materials either in case of their use in total radiation absorption or of neutrons to a suitable velocity. In consideration of that, an accurate docunuentation on this subject is presented and the measurements of absorption cross section of carbon, in the form of polgcrystalline graphite, exposed to a thermal neutron flux are examined critically. 17 references. (auth)" @default.
- W199409223 created "2016-06-24" @default.
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- W199409223 date "1958-06-01" @default.
- W199409223 modified "2023-09-28" @default.
- W199409223 title "THE ABSORPTION CROSS SECTION OF ELEMENTARY CARBON AND POLYCRYSTALLINE GRAPHITE" @default.
- W199409223 hasPublicationYear "1958" @default.
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