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Nuclear Reaction Data and Evaluated Data Libraries: Evaluation

Average Total Neutron Cross. Section of 233U, 235U and 239Pu from ORELA Transmission Measurements and Statistical Model Analysis of the Data

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Pages 84-87 | Published online: 27 Aug 2014
 

Abstract

The average total neutron cross sections of 233U, 235U, and 239Pu were obtained from transmission measurements in the unresolved resonance region up to several hundred keV neutron energy. The method used for the calculation of the selfshielding effect is described. A statistical model analysis of the results was performed and the s-, p- and d-wave neutron strength functions were obtained.

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