A COMPUTER PROGRAM TO SOLVE THE MULTIGROUP DIFFUSION EQUATIONS

Technical Report · Thu Mar 01 04:00:00 EST 1962

OSTI ID:4828935

Hassitt, A

A program, which solves the multigroup diffusion equations in two dimensions (RZ, XY, R THETA ) and in one dimension (slab, cylindrical or spherical geometry) on the IBM 704 or 7090 computer, is described. Up to 1OO energy groups may be used and neutrons may scatter from any group to any other. The program will compute the k effective of the system, or alternatively it will search for criticality by varying material composition, or by varying the reactor buckling, or by moving spatial boundaries. It will also solve source type problems. There is a standard print of final flux values. There is also a powerful general output routine, which is in fact a compiler. Output instructions are given in algebraic form, as part of the data to the program. The user can easily direct the processing of results so that complicated summing and integrating of the results can be done. Cross-sections may be put in directly or they may be obtained from the multigroup library in the program: a group condensation program is provided. (auth)

• Research Organization: United Kingdom Atomic Energy Authority. Reactor Group, Risley, Lancs, England
• NSA Number: NSA-16-024763
• OSTI ID: 4828935
• Report Number(s): TRG-Report-229
• Country of Publication: United Kingdom
• Language: English

Related Subjects

BUCKLING
COMPUTERS
CRITICALITY
DIFFERENTIAL EQUATIONS
DIFFUSION
DIGITAL SYSTEMS
GROUP THEORY
IBM 704
IBM 7090
NEUTRON FLUX
NEUTRONS
PHYSICS
PROGRAMMING
VARIATIONS