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Evaluation of the fission and capture cross sections of 240Pu; and 241Pu for ENDF/B-V. [10/sup -5/ eV to 20 MeV]

Conference ·
OSTI ID:5696900
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.
Research Organization:
Oak Ridge National Lab., TN (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5696900
Report Number(s):
CONF-791058--37
Country of Publication:
United States
Language:
English

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