Analysis of ORNL neutron transport benchmark experiments in thick sodium using IGC-S3 set

Full text: The newly prepared ENDF/B-VI based (175n, 42γ) coupled cross section set, IGC-S3, has been used in the analysis of neutron transmission benchmark experiments through 5 and 10 feet sodium, performed at Tower Shielding Facility of Oak Ridge National Laboratory, U.S.A. The neutron source was a collimated beam from the Tower shielding reactor and the integral flux measurements of transmitted neutrons were made using various 'Bonner' ball neutron detectors. The calculated transmitted scalar fluxes are converted into 'Bonner' ball count rates using its reported response functions. The calculated count rates are within the experimental errors and better than those obtained using DLC-37 set. The results showed that IGC-S3 set would provide better shield design as compared to DLC-37 set, for transport through sodium