BUGTRI; two-dimensional multigroup diffusion and burnup in triangular geometries. [UNIVAC1108; FORTRAN IV and Assembly language]

Technical Report ·

OSTI ID:6484567

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; Redfield, J A; Murphy,; Todt, F

The 2-dimensional multigroup, neutron diffusion theory equations for triangular geometry are solved to obtain the multiplication factor and the spatial flux and power distributions. Complete reactor life histories with partial refueling at a number of reload time-points can be calculated. The depletion scheme of all burnable nuclides is specified by the user at execution time. A regionwise depletion scheme is used. Concentration dependent self-shielding factors may be applied to any nuclide.UNIVAC1108; FORTRAN IV and Assembly language; EXEC2, GAX23; 65,536 words of core storage, 2 million words of drum storage on one data channel, 3 tape units, and a peripheral printer.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• OSTI ID: 6484567
• Report Number(s): ANL/NESC-439; ON: DE83048439
• 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
CONFIGURATION
DIFFERENTIAL EQUATIONS
DIFFUSION
EQUATIONS
HEXAGONAL CONFIGURATION
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
POWER DISTRIBUTION
RADIATION FLUX
TRANSPORT THEORY
TRIANGULAR CONFIGURATION
TWO-DIMENSIONAL CALCULATIONS