GAMTRI; two-dimensional, multigroup, diffusion triangular mesh geometries. [UNIVAC1108; FORTRAN IV (90%) and Assembly language (10%)]

Technical Report ·

OSTI ID:6484605

Dorsey, J P; Froehlich, R

The homogeneous two-dimensional multigroup diffusion theory equations with arbitrary group-to-group scattering and arbitrary fission transfer are solved for heterogeneous assemblies in (uniform mesh) triangular geometry. Homogeneous logarithmic boundary conditions are used at the outer surface of non-diffusion regions. The results include the group- and point-dependent neutron fluxes, the power distribution, the neutron multiplication factor, and a detailed neutron balance.UNIVAC1108; FORTRAN IV (90%) and Assembly language (10%); EXEC2, General Atomic Version GAX 23; 65,536 words of core storage, 3 tape units on 1 data channel, 1,572,864 words of drum storage from 1 data channel, and a peripheral printer-punch..

• Research Organization: General Atomic Co., San Diego, CA (USA)
• OSTI ID: 6484605
• Report Number(s): ANL/NESC-401; ON: DE83048401
• Country of Publication: United States
• Language: English

Related Subjects

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