Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

A MONTE CARLO CODE FOR THE TRANSPORT OF NEUTRONS

Technical Report ·
DOI:https://doi.org/10.2172/4166323· OSTI ID:4166323
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a uniform heterogeneous lattice of cylindrical fuel assemblies. Models of the geometric and physical processes are used to obtain the neutron age and migration area; the flux as a function of position, energy, and direction; and absorption data from which thermal utilization and the multiplication constant k may be calculated. (auth)
Research Organization:
Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
NSA Number:
NSA-14-008891
OSTI ID:
4166323
Report Number(s):
DP-446
Country of Publication:
United States
Language:
English