R-matrix Analysis of /sup 239/Pu Neutron Cross Sections in the Energy Range Up to 1000 EV.
R-matrix Analysis of /sup 239/Pu Neutron Cross Sections in the Energy Range Up to 1000 EV.

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Published: 1989

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The report is a description of the analysis of the /sup 239/Pu neutron cross sections in the resolved resonance region using the multilevel-multichannel Reich-Moore code SAMMY. The resonance parameters were obtained in the energy range up to 1000 eV. The table of the resonance parameters is given with some statistical properties of the parameters. Tabulated and graphical comparisons between the experimental data and the calculated cross sections are given. The results are available in ENDF/B-V format and will be proposed for the evaluated data libraries JEF2 and ENDF/B-VI. 24 refs., 23 figs., 16 tabs.

R-matrix Analyses of the 235U and 239Pu Neutron Cross Sections
R-matrix Analyses of the 235U and 239Pu Neutron Cross Sections

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Publisher:

Published: 1988

Total Pages:

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The resonance parameter analysis code SAMMY was used to perform consistent resonance analyses of several 235U and 239Pu fission and capture cross section and transmission measurements up to 110 eV for 235U and up to 1 keV for 239Pu. The method of analysis, the measurement selection and the results are briefly outlined in this paper.

R-matrix Analysis of the 24°Pu Neutron Cross Sections in the Thermal to 5700 EV Energy Range
R-matrix Analysis of the 24°Pu Neutron Cross Sections in the Thermal to 5700 EV Energy Range

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Published: 1997

Total Pages: 57

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Resonance analysis of high resolution neutron transmission data and of fission cross sections were performed in the neutron energy range from the thermal regions to 5,700 eV by using the Reich-Moore Bayesian code SAMMY. The experimental data base is described and the method of analysis is given. The experimental data were carefully examined in order to identify more resonances than those found in the current evaluated data files. The statistical properties of the resonance parameters are given. A new set of the average values of the parameters is proposed, which could be used for calculation of the average cross sections in the unresolved resonance region. The resonance parameters are available IN ENDF-6 format at the national or international data centers.