GAKIT; one-dimensional, multigroup kinetics with temperature feedback. [UNIVAC1108; FORTRAN IV]

Technical Report ·

OSTI ID:6423358

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,; Merrill, M H

GAKIT solves the multigroup, one-dimensional, time-dependent diffusion theory kinetics equations including delayed neutron effects and temperature feedback based on two-dimensional heat transfer calculations. For the one-dimensional multigroup kinetics equations an arbitrary scattering matrix and arbitrary fission transfer are allowed, and plane, cylindrical, or spherical geometry can be used. A piecewise linear time-dependent inhomogeneous source can be specified. Feedback is available from xenon buildup and temperature dependence of cross sections. The heat transfer calculation is performed for two-dimensional r-z fuel element models assuming predetermined axial power shape functions and time-dependent power amplitudes obtained from the one-dimensional kinetics calculations. For the fuel elements average fuel and moderator temperatures are calculated which determine, based on tables, the temperature-dependent cross sections. Transients may be introduced by step changes of cross sections, by piecewise linear time-dependent cross sections (rod withdrawal accidents), by step changes of the flow rates or by step changes of the coolant inlet temperatures.UNIVAC1108; FORTRAN IV; EXEC2, GAX 23, but any other system with a segmenting facility can be used; 65,536 words of core storage and the facility for segmenting programs.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• OSTI ID: 6423358
• Report Number(s): ANL/NESC-370; ON: DE83048370
• 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
DIFFUSION
ENERGY TRANSFER
EQUATIONS
FUEL ELEMENTS
G CODES
HEAT TRANSFER
KINETICS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
REACTOR COMPONENTS
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS