Published March 8, 1985 | Version v1
Miscellaneous

STAR, Fuel Management of BWR

Description

1 - Description of program or function: STAR is a one-group three- dimensional (x,y,z) coarse-mesh neutron diffusion theory code. It has a realistic thermal hydraulic model. The neutronic model of the code contains a kernel derived from a finite difference form of the coarse-mesh diffusion equation. Equations are written in terms of fission neutron sources rather than fluxes. One-group lattice parameters required are k-infinite and migration area as a function of burnup and steam void fraction. The code is useful for working out control rod patterns and performing reload pattern studies for boiling water reactors (BWR). The code computes the eigenvalue (keff) and the power distribution using an iterative procedure. 2 - Method of solution: Coarse-mesh finite difference method. 3 - Restrictions on the complexity of the problem: The code is written with variable dimensioning. About 20 K of memory is required for the program instructions. A problem having 1700 mesh points requires about 22 K for its major array size

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/iaea0882.html

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2 refs.