STAR, Fuel Management of BWR
Creators
- 1. Bhabha Atomic Research Centre, TROMBAY, Bombay - 400 085 (India)
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.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40047934
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Computer Program Description, Non-conventional Literature
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER PROGRAM DOCUMENTATION; CONTROL ELEMENTS; EIGENVALUES; FINITE DIFFERENCE METHOD; FISSION NEUTRONS; FUEL MANAGEMENT; LATTICE PARAMETERS; MIGRATION LENGTH; NEUTRON DIFFUSION EQUATION; POWER DISTRIBUTION; S CODES; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; VOID FRACTION; WEBSITES
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DIMENSIONS; DOCUMENT TYPES; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; FLUID MECHANICS; HADRONS; HYDRAULICS; ITERATIVE METHODS; LENGTH; MANAGEMENT; MATHEMATICAL SOLUTIONS; MECHANICS; NEUTRONS; NUCLEAR MATERIALS MANAGEMENT; NUCLEONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.