
Accession Number : AD0756290
Title : ANTE 3  A FORTRAN Computer Code for the Solution of the Adjoint Neutron Transport Equation by the Monte Carlo Technique.
Descriptive Note : Final rept.,
Corporate Author : MATHEMATICAL APPLICATIONS GROUP INC ELMSFORD N Y
Personal Author(s) : Cohen,Martin O. ; Beer,Mendel
Report Date : OCT 1972
Pagination or Media Count : 175
Abstract : ANTE3 is a FORTRAN code designed to solve the timedependent neutron transport equation in a threedimensional geometry by the adjoint Monte Carlo technique. The code uses point energy cross section data derived from the ENDF 3 libraries. In addition to theoretical discussions, a complete description of computer input and output is presented. ANTE3 is written in FORTRAN 4 and is presently operational on a CDC6600 digital computer. (Author)
Descriptors : (*NEUTRON TRANSPORT THEORY, *COMPUTER PROGRAMMING), MONTE CARLO METHOD, GEOMETRY, COMBINATORIAL ANALYSIS, NEUTRON SCATTERING, NUCLEAR CROSS SECTIONS, FISSION, STATISTICAL ANALYSIS, PROBABILITY
Subject Categories : Computer Programming and Software
Fission Reactor Physics
Nuclear Physics & Elementary Particle Physics
Distribution Statement : APPROVED FOR PUBLIC RELEASE