학술논문
A MONTE CARLO CODE FOR THE TRANSPORT OF NEUTRONS
Document Type
Technical Report
Author
Source
Other Information: Orig. Receipt Date: 31-DEC-60
Subject
Language
English
Abstract
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)