Actinide Cross Section Evaluations
Actinide Cross Section Evaluations

Author: D. A. Brown

Publisher:

Published: 2004

Total Pages: 7

ISBN-13:

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The Livermore Computational Nuclear Physics group is charged with producing updated neutron incident cross section evaluations for all the actinides in the coming year, concentrating on neutron induced fission, neutron capture and (n,2n) cross sections. We attack this daunting task either by adopting other recent evaluations or by performing our own. Owing to the large number of nuclei involved, we seek to automate this process as much as possible. For this purpose, we have developed a series of computer codes: x41, an interface to the EXFOR database, fete, a code that translates ENDF/B formatted evaluations into a computationally convenient form, and da{_}fit, a fitting code that takes all relevant EXFOR data for a reaction or set of reactions and performs a generalized least square fit to them, subject to various constraints and other prior information.

Evaluation and Testing of Actinide Cross Section Data. Final Report. Research Project Number RP707-2. [Summaries of Research Activities at Savannah River Laboratory].
Evaluation and Testing of Actinide Cross Section Data. Final Report. Research Project Number RP707-2. [Summaries of Research Activities at Savannah River Laboratory].

Author:

Publisher:

Published: 1979

Total Pages:

ISBN-13:

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The neutron cross section data below 10 keV for 242Cm, 245Cm, and 249Bk were evaluated and put into ENDF/B format. The new evaluations supersede the first release of ENDF/B-V and include both the average neutrons per fission, anti .nu., and cross section data for neutron scattering, capture, and fission as functions of energy. The evaluated data are available through the National Nuclear Data Center, Brookhaven National Laboratory. The evaluated cross sections were successfully tested against a limited amount of integral and production data. In addition, the thermal region of the ENDF/B-V evaluation of 241AM was tested against Savannah River Laboratory (SRL) integral data. 33 references.

Theory in Evaluation of Actinide Fission and Capture Cross Sections
Theory in Evaluation of Actinide Fission and Capture Cross Sections

Author:

Publisher:

Published: 2004

Total Pages: 7

ISBN-13:

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The authors discuss the possibilities and limitations of the use of theory as a tool in the evaluation of actinide fission and capture cross-sections. They consider especially the target 235U as an example. They emphasize the roles of intermediate structure in the fission cross-section and of level width fluctuations in both intermediate structure and fine structure, noting that these lead to a breakdown of Hauser-Feshbach theory at sub-barrier and near barrier energies. At higher energies (where fluctuation-averaged Hauser-Feshbach theory is applicable) semi-quantitative and intuitive representations of transition state spectra and barrier level density functions have to be tested against experimental data wherever these are available. Adjustment of the fission cross-section against inelastic scattering to the much better known levels of the residual nucleus should then lead to a fairly sound estimate of the capture cross-section. They compare such estimates with evaluated and experimental data for 235U.

Standard reference and other important nuclear data by the cross section evaluation working group
Standard reference and other important nuclear data by the cross section evaluation working group

Author: Brookhaven National Laboratory

Publisher:

Published: 1979

Total Pages:

ISBN-13:

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This report is a current review of the status of standard reference and other important nuclear data pointing out data discrepancies, recommending new measurements, and comparing the current version of ENDF/B with data. Neutron reactions with 1H, 3H, 6Li, 1°B, 12C, 59Co, 8°Kr, 136Xe, 153Eu, and 197Au are included, along with reaction and other data for the actinide nuclei. Cross sections, spectra, etc., are given for some of the nuclides considered. (RWR).