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- W2000970138 abstract "Neutron capture and fission reaction cross sections are usually measured relative to a standard basis. The most common absolute cross sections which are used in the thermal neutron energy region are /sup 197/Au and /sup 59/Co for capture reactions and /sup 235/U and /sup 239/Pu for fission reactions. Values for these four cross sections have been compiled and evaluated for the purpose of recommending standard values. 24 refs., 5 tabs. (WRF)" @default.
- W2000970138 created "2016-06-24" @default.
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- W2000970138 date "1989-01-01" @default.
- W2000970138 modified "2023-09-26" @default.
- W2000970138 title "Re-examination of 2200 metre/second cross section experiments for neutron capture and fission standards" @default.
- W2000970138 doi "https://doi.org/10.1351/pac198961081505" @default.
- W2000970138 hasPublicationYear "1989" @default.
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