Sensitivity of the Transport of 14-MeV Neutrons to the Nitrogen Elastic Angular Distribution,
Abstract
Calculations have been made to determine the radiation fields that would be generated by the transport of 14 MeV neutrons from a monodirectional point source in uniform nitrogen using two different cross section sets. One set was compiled from the ENDF/B Round-2 nuclear data file. The other set was compiled from the same ENDF/B Round-2 file; however, the shape of the elastic angular distribution was replaced by that of the ENDF/B Round-1 angular distribution. The correlated-sampling, Monte-Carlo, neutron-transport code SAMCEP was used for the calculations in order to facilitate more meaningful comparisons between the calculated answers of the two problems. (Modified author abstract)
Document Details
- Document Type
- Technical Report
- Publication Date
- Sep 01, 1973
- Accession Number
- AD0769712
Entities
People
- William B. Beverly
Organizations
- Ballistic Research Laboratory