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Journal Articles

R-matrix analysis of neutron effective total cross section, fission cross section and capture cross section of $$^{233}$$U in the energy range from thermal to 150 eV

H.Derrien*

Journal of Nuclear Science and Technology, 31(5), p.379 - 397, 1994/00

https://doi.org/10.3327/jnst.31.379
 Times Cited Count：9 Percentile：63.31(Nuclear Science & Technology)

no abstracts in English

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