BISYN; two-dimensional, multigroup diffusion synthesis calculations. [GE635; UNIVAC1108; FORTRAN IV]

Technical Report ·

OSTI ID:6484860

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Koppel, J U; Triplett, J R; Lynn, L L; Waldman, L A; Goldberg, I; Greebler, P; Kelley, M D; Davis, R A; Keck, C E; Duncan, W A

BISYN solves the two-dimensional, multigroup, neutron diffusion equations in x-y or r-z geometry using a noniterative synthesis method. This approach is designed to greatly reduce the computer cost of running two-dimensional multigroup problems at the risk of some loss in accuracy of the detailed flux distribution.GE635;UNIVAC1108; FORTRAN IV; GECOS III, SDL1 (GE635) and EXEC2 (UNIVAC1108); 47,000 words of memory, disk, drum, and 2 tapes for the GE635. 54K of fast memory, 2 tape drives, 510,000 words of peripheral storage and the ability to segment for the UNIVAC1108.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Energy Div.
• OSTI ID: 6484860
• Report Number(s): ANL/NESC-287; ON: DE83048287
• Country of Publication: United States
• Language: English

Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
B CODES
COMPUTER CODES
DIFFERENTIAL EQUATIONS
EQUATIONS
FLUX SYNTHESIS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS