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Neutron Fission Cross Sections of 239Pu and 240Pu Relative to 235U

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 248-259

Technical Paper / dx.doi.org/10.13182/NSE83-A17793

The ratios of the neutron fission cross sections σf(240Pu)/σf(239Pu), σf(240Pu)/σf(235U), and σf(239Pu)/σf(235U) have been measured simultaneously with a multiplate ionization fission chamber using the Oak Ridge Electron Linear Accelerator as a neutron source over the neutron energy range from 5 keV to 20 MeV. The 240Pu ratio data are in overall agreement with ENDF/B-V with exceptions in relatively narrow neutron energy regions. Below 150 keV and from 10 to 20 MeV, the present 239Pu/235U fission ratios indicate significant discrepancies when compared to ENDF/B-V. These ratios are important for thermal and fast reactor applications.