Actions for Evaluation of the fission and capture cross sections of <sup>240<

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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] [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1979.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 5 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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.
Report Numbers
E 1.99:conf-791058--37
conf-791058--37
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1979.
"conf-791058--37"
International conference on nuclear cross sections for technology, Knoxville, TN, USA, 22 Oct 1979.
Weston, L. W.; Wright, R. Q.
Funding Information
W-7405-ENG-26
View MARC record | catkey: 14673116