M0176--A FORTRAN PROGRAM TO SOLVE SEVERAL P-APPROXIMATIONS TO THE FEW GROUP NEUTRON TRANSPORT EQUATION IN SLAB GEOMETRY

Technical Report · Sun Apr 01 04:00:00 EST 1962

OSTI ID:4821556

Cantwell, R M

M0176 is a FORTRAN program which solves the neutron transport equation in a slab geometry in a few-group approximation. Fast groups are P-1 or P-3, while thermal groups are P-1 or double P-1. A variational P-1 thermal treatment, using a transformed SWAKRAUM representation, is included as an option. Boundary conditions are general. Eigenvalue, slowing down, or purely thermal problems are done. Strategy of solution is quite variable. (auth)

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-16-023274
• OSTI ID: 4821556
• Report Number(s): WAPD-TM-320
• Country of Publication: United States
• Language: English

Related Subjects

CONFIGURATION
DIFFERENTIAL EQUATIONS
EIGENVALUES
FAST NEUTRONS
GROUP THEORY
MATHEMATICS
NEUTRONS
PLATES
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
SLOWDOWN
THERMAL NEUTRONS
TRANSPORT THEORY