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Fast neutron capture cross sections for fission product isotopes

Hanford Engineering Development Lab., Richland, Wash. (USA), F Schmittroth, R Schenter

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Abstract

Calculated average capture cross sections are given from 10 eV to 15 MeV to be used as a basis for revising and extending the ENDF/B-IV data files.Thirty-nine fission product isotopes^ plus Au^^^j are included.The results were obtained by statistical model calculations that were adjusted as seemed necessary by the available capture data.For those isotopes studied earlier, the major revision is the use of new estimates for the neutron resonance spacings.Integral cross sections are computed and compared with values from the Coupled Fast Reactivity Measurement Facility (CFEMF).

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Calculated average capture cross sections are given from 10 eV to 15 MeV to be used as a basis for revising and extending the ENDF/B-IV data files.Thirty-nine fission product isotopes^ plus Au^^^j are included.The results were obtained by statistical model calculations that were adjusted as seemed necessary by the available capture data.For those isotopes studied earlier, the major revision is the use of new estimates for the neutron resonance spacings.Integral cross sections are computed and compared with values from the Coupled Fast Reactivity Measurement Facility (CFEMF).

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Available abstract

Calculated average capture cross sections are given from 10 eV to 15 MeV to be used as a basis for revising and extending the ENDF/B-IV data files.Thirty-nine fission product isotopes^ plus Au^^^j are included.The results were obtained by statistical model calculations that were adjusted as seemed necessary by the available capture data.For those isotopes studied earlier, the major revision is the use of new estimates for the neutron resonance spacings.Integral cross sections are computed and compared with values from the Coupled Fast Reactivity Measurement Facility (CFEMF).

Key concepts: Neutron, Nuclear physics, Californium, Nuclear transmutation, Curium, Neutron cross section, Neutron generator, Neutron temperature

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