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 time-dependent neutron transport equation in a three-dimensional 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 CDC-6600 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