Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

Derrien, H

Oak Ridge National Laboratory

关键词: Total Cross Sections;    Energy Range;    Self-Shielding;    Neutrons;    Cross Sections;   

DOI  :  10.2172/861677
RP-ID  :  ORNL/TM-2003/291
RP-ID  :  DE-AC05-00OR22725
RP-ID  :  861677

美国|英语

来源: UNT Digital Library

【 摘 要 】

Average values of the neutron total cross sections of {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu have been obtained in the unresolved resonance energy range from high-resolution transmission measurements performed at ORELA in the past two decades. The cross sections were generated by correcting the effective total cross sections for the self-shielding effects due to the resonance structure of the data. The self-shielding factors were found by calculating the effective and true cross sections with the computer code SAMMY for the same Doppler and resolution conditions as for the transmission measurements, using an appropriate set of resonance parameters. Our results are compared to results of previous measurements and to the current ENDF/B-VI data.