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].

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Published: 1979

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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.


Testing New Actinide Cross Sections Proposed for ENDF

Testing New Actinide Cross Sections Proposed for ENDF

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Published: 2004

Total Pages: 7

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Our Nuclear Physics Group has worked over the last several years to improve the ENDF/B actinide cross sections, especially as measured against the famous series of fast-spectrum critical experiments performed at Los Alamos under such names as Godiva, Jezebel, the Flattops, and Bigten. The new evaluations include changes in the high-energy fission cross sections, nubar, elastic scattering, inelastic scattering, fission spectra, and delayed neutrons that combine to significantly improve the calculated results for the Los Alamos critical assemblies. As a happy byproduct of this work, we found that the new evaluations also removed about half of a long-standing discrepancy in calculations of thermal-reactor critical experiments using lattices of low-enriched uranium oxide rods. In the meantime, work at the Oak Ridge National Laboratory has resulted in new proposed resonance parameters for U238. When these low-energy data are combined with the new high-energy data from Los Alamos, they have the effect of removing most of the rest of the problem for thermal lattices. Although more work will be done at both Los Alamos and Oak Ridge, including making the evaluations consistent with the new standards, the results presented in this talk provide promise that ENDF/B-VII will result in good improvements for users at both high and low neutron energies.


Theory in Evaluation of Actinide Fission and Capture Cross Sections

Theory in Evaluation of Actinide Fission and Capture Cross Sections

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Published: 2004

Total Pages: 7

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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.


Cross-section Evaluation Utilizing Integral Reaction-rate Measurements in Fast Neutron Fields

Cross-section Evaluation Utilizing Integral Reaction-rate Measurements in Fast Neutron Fields

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Published: 1980

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The role of integral reaction-rate data for cross-section evaluation is reviewed. The subset of integral data considered comprises integral reaction rates measured for dosimeter, fission-product, and actinide-type materials irradiated in reactor dosimetry fast neutron benchmark fields and in the EBR-II. Utilization of these integral data for integral testing, multigroup cross-section adjustment and pointwise cross section adjustment is treated in some detail. Examples are given that illustrate the importance of considering a priori uncertainty and correlation information for these analyses. 3 figures, 3 tables.