Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV].
Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV].

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Published: 1979

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Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for /sup 240/Pu and /sup 241/Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10/sup -5/ eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in /sup 240/Pu and the 0.3-eV resonance in /sup 241/Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.

Evaluation of the Fission and Capture Cross Sections of 24°Pu ; and 241Pu for ENDF
Evaluation of the Fission and Capture Cross Sections of 24°Pu ; and 241Pu for ENDF

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Published: 1979

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Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for 24°Pu and 241Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10−5 eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in 24°Pu and the 0.3-eV resonance in 241Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.

Evaluation of the 235U Fission Cross-section from 100 EV to 20 MeV. [Cross Sections, Error Estimates].
Evaluation of the 235U Fission Cross-section from 100 EV to 20 MeV. [Cross Sections, Error Estimates].

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Published: 1976

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The evaluation of the 235U fission cross section from 100 eV to 20 MeV for ENDF/B-V is described. The evaluated average cross sections from 100 eV to 200 keV are given, and it is proposed to include structure in the cross section in this energy region. Above 200 keV, the cross section is given as a smooth curve, and is recommended as a standard. Preliminary error estimates in the cross section are also given.

Evaluation of 232Th for ENDF
Evaluation of 232Th for ENDF

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Published: 1981

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The evaluation of neutron and gamma ray production cross sections of 232Th from 10−5 eV to 20 MeV is described, and the parts contributed by the author to the evaluation are discussed. All available new data have been included and the procedures used to assess the experimental data and adopt recommended values are described.

Evaluated (n, P) Cross Sections of /sup 46/Ti /sup 47/Ti and /sup 48/Ti
Evaluated (n, P) Cross Sections of /sup 46/Ti /sup 47/Ti and /sup 48/Ti

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Published: 1977

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Microscopic evaluated neutron cross sections for the reactions /sup 46/Ti(n;p)/sup 46/Sc, /sup 47/Ti(n;p)/sup 47/Sc and /sup 48/Ti(n;p)/sup 48/Sc are obtained from threshold (or zero energy) to 20 MeV. The results are presented in graphical and numerical (ENDF format) form. The microscopic evaluated cross sections are compared with measured fission-spectrum-averaged values.

The Fission Cross Section Ratios and Error Analysis for Ten Thorium, Uranium, Neptunium and Plutonium Isotopes at 14. 74 MeV Neutron Energy
The Fission Cross Section Ratios and Error Analysis for Ten Thorium, Uranium, Neptunium and Plutonium Isotopes at 14. 74 MeV Neutron Energy

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Published: 1987

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The error information from the recent measurements of the fission cross section ratios of nine isotopes, 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu, and 242Pu, relative to 235U at 14.74 MeV neutron energy was used to calculate their correlations. The remaining 36 non-trivial and non-reciprocal cross section ratios and their errors were determined and compared to evaluated (ENDF/B-V) values. There are serious differences but it was concluded that the reduction of three of the evaluated cross sections would remove most of them. The cross sections to be reduced are 23°Th - 13%, 237Np - 9.6% and 239Pu - 7.6%. 5 refs., 6 tabs.

Evaluation of N + 242Pu Reactions from 10 KeV to 20 MeV. [Data Compilation, Cross Sections, Angular Distributions].
Evaluation of N + 242Pu Reactions from 10 KeV to 20 MeV. [Data Compilation, Cross Sections, Angular Distributions].

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Published: 1978

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An evaluation of the n + 242Pu cross sections is presented for the neutron energy range of 10 keV to 20 MeV. The total fission and radiative capture cross sections are based upon experimental measurements of 242Pu. The remaining cross sections, together with the elastic and inelastic angular distributions to low lying states were calculated using various reaction models. An expression is presented for the energy dependence of the average number of neutrons produced per fission. The results were placed in ENDF/B-V format and combined with a recent evaluation of data below 10 keV by the Hanford Engineering Development Laboratory, so that a complete data set covering the energy range of 10−5 eV to 20 MeV is available. 41 references.