Measurement and Analysis of the Neutron-induced Fission Cross Sections of 247Cm, 25°Cr and 254Es

Measurement and Analysis of the Neutron-induced Fission Cross Sections of 247Cm, 25°Cr and 254Es
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Total Pages: 3
Release: 1994
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A series of fission cross section measurements were performed on 247Cm, 25°Cf and 254Es. This paper summarizes the most recent results and details the resonance parameter analysis done on 247Cm.

Government Reports Annual Index

Government Reports Annual Index
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Total Pages: 1372
Release: 1994
Genre: Government reports announcements & index
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Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites

Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites
Author: W. Younes
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Total Pages:
Release: 2003
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Cross sections for neutron-induced fission of {sup 231,233}Th, {sup 234,235,236,237,239}U, and {sup 240,241,243}Pu are presented in tabular form for incident neutron energies of 0.1 {le} E{sub n}(MeV) {le} 2.5. The cross sections were obtained by converting measured fission probabilities from (t, pf) reactions on mass-A targets to (n, f) cross sections on mass-A + 1 neutron targets, by using modeling to compensate for the differences in the reaction mechanisms. Data from Britt et al. were used for the {sup 234}U(t, pf) reaction, from Cramer et al. for the {sup 230,232}Th(t, pf), {sup 236,238}U(t, pf), and {sup 240,242}Pu(t, pf) reactions, and from Britt et al. for the {sup 233,235}U(t, pf) and {sup 239}Pu(t, pf) reactions. The fission probabilities P{sub (t, pf)}(E{sub x}), measured as a function of excitation energy E{sub x} of the compound system formed by the (t, p) reaction, are listed in the tables with the corresponding deduced cross sections as a function of incident neutron energy E{sub n}, {sigma}{sub (n, f)}(E{sub n}). The excitation energy and incident neutron energy are related by E{sub x} = E{sub n} + B{sub n}, where B{sub n}, where B{sub n} is the neutron binding energy. Comparison with ENDF/B-VI evaluations of the well-measured {sup 234,235,236}U(n, f) and {sup 240,241}Pu(n, f) cross sections confirms the accuracy of the present results within a 10% standard deviation above E{sub n} = 1 MeV. Below E{sub n} = 1 MeV, localized deviations of at most {+-} 20% are observed.

Fission Cross Section Ratios for Sup 233,234,236 U Relative to Sup 235 U from 0. 5 to 400 MeV.

Fission Cross Section Ratios for Sup 233,234,236 U Relative to Sup 235 U from 0. 5 to 400 MeV.
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Total Pages: 5
Release: 1991
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Neutron-induced fission cross section ratios from 0.5 to 400 MeV for samples of {sup 233, 234, 236}U relative to 235U have been measured at the WNR neutron Source at Los Alamos. The fission reaction rate was determined using a fast parallel plate ionization chamber at a 20-m flight path. Cross sections over most the energy range were also extracted using the neutron fluence determined with three different proton telescope arrangements. Those data provided the shape of the 235U(n, f) cross section relative to the hydrogen scattering cross section. That shape was then normalized to the very accurately known value for 235U(n, f) at 14.1 MeV to allow us to obtain cross section section values from the ratio data and our values for 235U(n, f). 6 refs., 1 fig.

Calculated Neutron-induced Cross Sections for /sup 52/Cr from 1 to 20 MeV and Comparisons with Experiments

Calculated Neutron-induced Cross Sections for /sup 52/Cr from 1 to 20 MeV and Comparisons with Experiments
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Release: 1987
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Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 52/Cr for incident energies from 1 to 20 MeV. The input parameters for the model codes were determined through analysis of experimental data in this energy region. Discussion of the models used, the input data, the resulting calculations, extensive comparisons to measured data, and comparisons to the Evaluated Nuclear Data File (ENDF/B-V) for Cr (MAT 1324) are included in this report. 103 refs., 67 figs., 12 tabs.

Calculated Neutron-induced Cross Sections for

Calculated Neutron-induced Cross Sections for
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Release: 1985
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Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 63,65/Cu, /sup 58,60/Ni, and 52Cr for incident energies from 1 to 20 MeV. The input parameters for the model codes determined through analysis of experimental data in this energy region. The models used, the input data, the resulting calculations, and comparisons with measured data are discussed. 15 refs.