ISSN Online: 2377-424X
ISBN Print: 0-89116-299-2
International Heat Transfer Conference 7
TRANSIENT THERMAL-HYDRAULIC ANALYSIS USING A MODIFIED VERSION OF COBRA IV
Sinopsis
Computational thermal-hydraulic analysis of the fuel rod arrays in the Gas-Cooled Fast Breeder Reactor has been severely limited in the past by some of the inherent characteristics of the GCFR system. The primary transient analysis code currently in use, COBRA GCFR, employs a multiple axial march solution of the conservation equations. The lateral crossflow distributions are determined by an iterative technique which is time consuming when applied to GCFR analysis.
An alternative numerical technique is designed that is based on the Modified Advanced Theta method developed for water reactor systems. An iterative method is designed that operates on the lateral pressure fields existing at each axial level, and the crossflows are then inferred. The method is implemented into a problem-directed computer code capable of either single-pass or multi-pass axial marching schemes. This code, COBRA GCFR 4P/UT, has been exercised successfully on severe flow blockage situations, results of which indicate it is more efficient than its counterpart for GCFR analysis.
An alternative numerical technique is designed that is based on the Modified Advanced Theta method developed for water reactor systems. An iterative method is designed that operates on the lateral pressure fields existing at each axial level, and the crossflows are then inferred. The method is implemented into a problem-directed computer code capable of either single-pass or multi-pass axial marching schemes. This code, COBRA GCFR 4P/UT, has been exercised successfully on severe flow blockage situations, results of which indicate it is more efficient than its counterpart for GCFR analysis.