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:

1972-10-01

Pagination or Media Count:

175.0

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 and Elementary Particle Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE