The SABRE code for fuel rod cluster thermohydraulics
Description
This paper describes the capabilities of the SABRE code for the calculation of single phase and two phase fluid flow and temperature in fuel pin bundles, discusses the methods used in the modelling and solution of the problem, and presents some results including comparison with experiments. The SABRE code permits calculation of steady-state or transient, single or two phase flows and the geometrical options include general representation of grids, wire wraps, multiple blockages, bowed pins, etc. The derivation and solution of the difference equations is discussed. Emphasis is given to the derivation of the spatial differences in triangular subchannel geometry, and the use of central, upward or vector upwind schemes. The method of solution of the difference equations is described for both steady state and transient problems. Together with these topics we consider the problems involved in turbulence modelling and how it is implemented in SABRE. This includes supporting work with a fine scale curvilinear coordinate programme to provide turbulence source data. The problem of modelling boiling flows is discussed, with particular reference to the numerical problems caused by the rapid density change on boiling. The final part of the paper presents applications of the code to the analysis of blockage situations, the study of flow and power transients and analysis of natural circulation within clusters to demonstrate the scope of the code and compare with available experimental results. The comparisons include the calculation of a flow pressure drop characteristic of a boiling channel showing the Ledinegg instability, examples of overpower and flow rundown transients which lead to coolant boiling, and calculation of natural circulation within a rod cluster. (orig./GL)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 82
- Journal Issue
- 2/3
- Series
- CODEN: NEDEA.;Nucl. Eng. Des.
- Journal Page Range
- 171-190
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 16027015
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BOILING; BOUNDARY CONDITIONS; FINITE DIFFERENCE METHOD; FLOW MODELS; FUEL ELEMENT CLUSTERS; GRIDS; HYDRAULICS; MESH GENERATION; REYNOLDS NUMBER; S CODES; THERMAL CONDUCTION; THERMODYNAMICS; TURBULENCE
- Descriptors DEC
- COMPUTER CODES; ELECTRODES; ENERGY TRANSFER; FUEL ASSEMBLIES; HEAT TRANSFER; ITERATIVE METHODS; MATHEMATICAL MODELS; NUMERICAL SOLUTION; PHASE TRANSFORMATIONS