Evaluation of the Fission and Capture Cross Sections of 24°Pu ; and 241Pu for ENDF
Author:
Publisher:
Published: 1979
Total Pages:
ISBN-13:
DOWNLOAD EBOOKSince there were appreciable new data which were not available for ENDF/B-IV, new evaluations for 24°Pu and 241Pu 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 10−5 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 24°Pu and the 0.3-eV resonance in 241Pu. 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.