GAMBLE5; two-dimensional, multigroup diffusion in xy and rz geometry. [UNIVAC1108; FORTRAN IV and Assembly language]

Technical Report ·

OSTI ID:6365405

Dorsey, J P; Froehlich, R

The homogeneous 2-dimensional multigroup diffusion theory equations with arbitrary group-to-group scattering and arbitrary fission transfer are solved for heterogeneous assemblies in x-y and r-z geometry. Homogeneous logarithmic boundary conditions are used at the outer surface of the assembly and at the surface of non-diffusion regions. The results include the group and point-dependent neutron fluxes, the power distribution, the neutron multiplication factor (k-effective), and a detailed neutron balance.UNIVAC1108; FORTRAN IV and Assembly language; VERSION IX and EXEC2, GAX23; 65,536 words of core storage and 3 tape units on one data channel, 1,572,864 words of FH-880 drum storage from one data channel, and a peripheral printer.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• OSTI ID: 6365405
• Report Number(s): ANL/NESC-222; ON: DE83048222
• 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
DIFFERENTIAL EQUATIONS
EQUATIONS
G CODES
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTIVITY
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS